Text

Annual Monitoring Report 2004 for Point Beach Nuclear Plant
	ML051580480
Person / Time
Site:	Point Beach
Issue date:	04/30/2005
From:	; Nuclear Management Co
To:	; Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209
	Download: ML051580480 (108)
	v • d • e

ANNUAL MONITORING REPORT 2004 NUCLEAR MANAGEMENT COMPANY, LLC POINT BEACH NUCLEAR PLANT 7

r S.

4 January 1, 2004, through December 31, 2004 April 2005

TABLE OF CONTENTS Executive Summary 1

Part A: Effluent Monitoring 1.0 Introduction 3

2.0 Radioactive Liquid Releases 4

3.0 Radioactive Airborne Releases 10 4.0 Radioactive Solid Waste Shipments 13 5.0 Nonradioactive Chemical Releases 16 6.0 Circulating Water System Operation 17 Part B: Miscellaneous Reporting Requirements 7.0 Additional Reporting Requirements 18 Part C: Radiological Environmental Monitoring 8.0 Introduction 19 9.0 Program Description 20 10.0 Results 32 11.0 Discussion 35 12.0 REMP Conclusion 41 Appendix A: Environmental, Inc. Midwest Laboratory, "Final Report for Point Beach Nuclear Plant."

i

TABLE OF TABLES Table 2-1 Comparison of 2004 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Table 2-2 Summary of Circulating Water Discharge Table 2-3 Isotopic Composition of Circulating Water Discharges (Curies)

Table 2-4 Subsoil System Drains - Tritium Summary Table 3-1 Comparison of 2004 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Table 3-2 Radioactive Airborne Release Summary Table 3-3 Isotopic Composition of Airborne Releases Table 4-1 Quantities and Types of Waste Shipped from PBNP Table 4-2 Estimated Solid Waste Major Radionuclide Composition Table 4-3 PBNP Radioactive Waste Shipments Table 6-1 Circulating Water System Operation for 2004 Table 9-1 PBNP REMP Sample Analysis and Frequency Table 9-2 PBNP REMP Sampling Locations Table 9-3 ISFSI Sampling Sites Table 9-4 Minimum Acceptable Sample Size Table 9-5 Deviations from Scheduled Sampling and Frequency Table 9-6 Sample Collection for the State of Wisconsin Table 10-1 Radiological Environmental Monitoring Results for 2004 Table 10-2 ISFSI Fence TLD Results for 2004 Table 11-1 Average Indicator TLD Results from 1993-2004 Table 11-2 Average ISFSI Fence TLD Results (mRl7days)

Table 11-3 Average TLD Results Surrounding the ISFSI (mR/7days)

Table 11-4 Average Gross Beta Measurements in Air Table 11-5 Average Gross Beta Concentrations in Soil 4

6 7

9 11 11 12 13 14 15 17 22 23 27 27 28 29 33 35 35 36 36 37 40 TABLE OF FIGURES Figure 9-1 Figure 9-2 Figure 9-3 Figure 11-1 Figure 11-2 PBNP REMP Sampling Sites Map of REMP Sampling Sites Located Around PBNP Enhanced Map Showing REMP Sampling Sites Closest to PBNP 2004 Airborne Gross Beta Concentrations (pCi/M3) vs. Time 2004 Airborne 1-131 Concentration Frequency Distribution 24 25 26 38 38 ii

I EXECUTIVE

SUMMARY

I This Annual Monitoring Report for the period of January 1, 2004, through December 31, 2004, is submitted in accordance with Point Beach Nuclear Plant (PBNP) Units 1 and 2 Technical Specification 5.6.2 and filed under Dockets 50-266 and 50-301 for Facility Operating Licenses DPR-24 and DPR-27, respectively. The report presents the results of effluent and environmental monitoring programs, solid waste shipments, non-radioactive chemical releases, and circulating water system operation.

During 2004, the following Curies (Ci) of radioactive material were released via the liquid and atmospheric pathways:

-Liquid Atmospheric Tritium (Ci) 608 60.5 Particulate (Ci) 0.023 0.000001 Noble Gas (Ci)

(-)

1.300

(-)Noble gases in the liquids are added to the atmospheric release totals.

Atmospheric particulate includes radioiodines in this table.

For the purpose of regulatory compliance with the effluent design objectives of Appendix I to 10 CFR 50, doses from effluents are calculated for the hypothetical maximally exposed individual (MEI) for each age group and compared to the Appendix I objectives. Doses less than or equal to the Appendix I values are considered to be evidence that PBNP releases are as low as reasonably achievable (ALARA). The maximum annual calculated doses in millirem (mrem) or millirad (mrad) are shown below and compared to the corresponding design objectives of 10 CFR 50, Appendix I.

LIQUID RELEASES Dose Categorv Whole body dose Organ dose Calculated Dose 0.0066 mrem 0.0066 mrem Appendix I Dose 6 mrem 20 mrem ATMOSPHERIC RELEASES Dose Categorv Organ dose Noble gas beta air dose Noble gas gamma ray air dose Noble gas dose to the skin Noble gas dose to the whole body Calculated Dose 0.024 mrem 0.00017 mrad 0.00041 nurad 0.00058 mrem 0.00039 mrem Appendix I Dose 30 mrem 40 mrad 20 mrad 30 mrem 10 mrem The results show that during 2004, the doses from PBNP effluents were a small percentage 1

( 0.11 % at the most) of the Appendix I design objectives and therefore operation of PBNP continues to be ALARA.

In addition to collecting and analyzing environmental samples, a survey of land use with respect to the location of dairy cattle was made pursuant to Section 2.5 of the PBNP Environmental Manual. As in previous years, no dairy cattle were found to be grazing at the site boundary.

Therefore, the assumption that cattle graze at the site boundary used in the evaluation of doses from PBNP effluents remains conservative.

The 2004 Radiological Environmental Monitoring Program (REMP) collected 805 samples for radiological analyses and 116 sets of thermoluminescent dosimeters (TLDs) to measure ambient radiation in the vicinity of PBNP and the Independent Spent Fuel Storage Installation (ISFSI).

Air monitoring from six different sites showed only background radioactivity from naturally occurring radionuclides. Terrestrial monitoring consisting of soil, vegetation, and milk found no influence from PBNP. Similarly, samples from the aquatic environment, consisting of lake and well water, fish, and algae, revealed no buildup of PBNP radionuclides released in liquid effluents. Therefore, these data show no plant effect on its environs.

As of December 2004, the ISFSI contained a total of 20 dry storage casks. Sixteen were the ventilated, vertical storage casks (VSC-24) from the previous years. During 2004, four new casks were transferred to the east side of the ISFSI. These were the NUHOMS, horizontally stacked storage modules. The subset of the PBNP REMP samples used to evaluate the environmental impact of the PBNP ISFSI showed no environmental impact from its operation.

The environmental monitoring conducted during 2004 confirms that the effluent control program at PBNP ensures that its operations minimally impact the environs.

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1.0 INTRODUCTION

The PBNP effluent monitoring program is designed to comply with federal regulations for ensuring the safe operation of PBNP with respect to releases of radioactive material to the environment and its subsequent impact on the public. 10 CFR 50.34a states that operations should be conducted to keep the levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). In 10 CFR 50, Appendix I, the Nuclear Regulatory Commission (NRC) provides the numerical values for what it considers to be the appropriate ALARA design objectives to which the licensee's calculated effluent doses may be compared. These doses are a small fraction of the dose limits specified by 10 CFR 20.1301 and lower than the Environmental Protection Agency (EPA) limits specified in 40 CFR 190.

10 CFR 20.1302 directs PBNP to make the appropriate surveys of radioactive materials in effluents released to unrestricted and controlled areas. Liquid wastes are monitored by inline radiation monitors as well as by isotopic analyses of samples of the waste stream prior to discharge from PBNP. Airborne releases of radioactive wastes are monitored in a similar manner. Furthermore, for both liquid and atmospheric releases, the appropriate portions of the radwaste treatment systems are used as required to keep releases ALARA.

Prior to release, results of isotopic analyses are used to adjust the release rate of discrete volumes of liquid and atmospheric wastes (from liquid waste holdup tanks and from gas decay tanks) such that the concentrations of radioactive material in the air and water beyond PBNP are below the PBNP Technical Specification concentration limits for liquid effluents and release rate limits for gaseous effluents.

Solid wastes are shipped offsite for disposal at NRC licensed facilities. The amount of radioactivity in the solid waste is determined prior to shipment in order to determine the proper shipping configuration as regulated by the Department of Transportation and the NRC.

Also operated at PBNP under the General License granted pursuant to 10 CFR 72.210 is an Independent Spent Fuel Storage Installation (ISFSI). The release of radioactive materials from the operation of the ISFSI must also comply with the limits of part 20 and the part 50 Appendix I design objectives. Per 10 CFR 72.44(d)(3), the results of radiological effluent monitoring are to be reported annually.* The dose criteria for effluents and direct radiation specified by 10 CFR 72.104 states that during normal operations and anticipated occurrences, the annual dose equivalent to any real individual Holders of a Part 72 license are allowed to submit the report required by 72.44(d)(3) concurrent with the effluent report required by 10 CFR 50.36a (a)(2). (

Reference:

64 FR 33178) 3

beyond the controlled area must not exceed 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other organ. The dose from naturally occurring radon and its decay products are exempt. Because the loading of the storage casks occurs within the primary auxiliary building of PBNP, the doses from effluents due to the loading process will be assessed and quantified as part of the PBNP Radiological Effluent Control Program.

2.0 RADIOACTIVE LIQUID RELEASES The release path to the environment contributing to radioactive liquid releases is circulating water discharge. A liquid waste treatment system in conjunction with administrative controls is used to minimize the impact on the environment and maintain doses to the public ALARA from the liquid releases.

2.1 Doses From Liquid Effluent Doses from liquid effluent are calculated using the methodology of the Offsite Dose Calculation Manual (ODCM). These calculated doses use parameters such as the amount of radioactive material released, the total volume of liquid, the total volume of dilution water, and usage factors (e.g., water and fish consumption, shoreline and swimming factors). These calculations produce a conservative estimation of the dose. For compliance with 10 CFR 50, Appendix I design objectives, the annual dose is calculated to the hypothetical maximally exposed individual (MI). The MEI is assumed to reside at the site boundary in the highest X/Q sector and is maximized with respect to occupancy, food consumption, and other uses of this area. As such, the MEI represents an individual with reasonable deviations from the average for the general population in the vicinity of PBNP. A comparison of the calculated doses to the 10 CFR 50, Appendix I design objectives is presented in Table 2-1. The conservatively calculated dose to the MEI is a very small fraction of the Appendix I design objective.

Table 2-1 Comparison of 2003 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Annual Limit [mrem]

Highest Total Calculated Dose [mrem]

% of Design Objective 6 (whole body) 0.0066 0.11 %

20 (any organ) 0.0066 0.03 %

4

2.2 2004 Circulating Water Radionuclide Release Summary Radioactive liquid releases via the circulating water discharge are summarized by individual source and total curies released on a monthly basis and presented in Table 2-2.

2.3 2004 Isotopic Composition of Circulating Water Discharges The isotopic composition of circulating water discharges during the current reporting period is presented in Table 2-3.

2.4 Subsoil Drain System Releases Tritium Summary The quarterly and annual results of monitoring the subsoil drains are presented in Table 2-4. No tritium was observed in any of the drains during 2004.

2.5 Changes to the Waste Liquid Treatment System in 2004 There were no changes to the liquid waste treatment system in 2004.

5

Table 2-2 Summary of Circulating Water Discharge January 1, 2004, through December 31, 2004 Total l Annual l

Jan Feb Mar Apr May Jun Jan-Jun Jul Aug.

Sep Oct Nov Dec Total Total Activity Released (Ci)

Gamma Scan (+Fe-S5) 1.45E-03 1.78E-03 1.52E-03 2.79E-03 3.68E-03 9.06E-03 2.03E-02 8.90E-04 3.65E-04 2.72E-04 2.55E-04 1.94E-04 3.97E-04 2.27E-02 Gross Alpha 5.63E-07 8.65E-07 O.OOE+00 O.OOE+0O O.OOE+00 O.OOE+00 1.43E-06 7.46E-07 O.OOE+00 0.00E+00 0.00E+00 2.95E-06 O.OOE+OO 5.12E-06 Tritium 1.97E+01 6.06E+-01 4.73E+01 2.07E+01 9.32E+01 2.46E+01 2.66E+02 1.23E+01 4.54E+01 1.37E+01 7.74E+01 11.32E+02 6.11 E+01 6.08E+02 Strontium (89/90/92) 0.002+00 0.00+00 0.00+00 0.00+00 0.00+00 0.00+00 0.002+00 0.002+00 O.OOE+00 O.OOE+00 0.002+00 0.00+00 0.002+00 O.OOE+00 Total Vol Released (gal)

Processed Waste 2.76E+04 7.37E+04 1.04E+05 1.01 E+05 1.41 E+05 1.33E+05 5.80E+05 3.52E+04 4.58E+04 4.29E+04 3.92E+04 9.74E+04 4.97E+04 8.91 E+05 Waste Water Effluent*

4.21 E+06 3.78E+06 4.72E+06 3.75E+06 3.72E+06 4.18E406 2.44E+07 4.05E+06 4.14E+06 4.12E+06 4.87E+06 5.07E+06 5.17E+06 5.18E+07 UI SG Blowdown 2.66E+06 2.50E+06 2.67E+06 2.70E+05 O.OOE+00 2.87E+06 1.10E+07 2.83E+06 2.38E+06 2.66E+06 2.59E+06 2.36E+06 2.61 E+06 2.64E+07 U2 SG Blowdown 2.66E+06 2.51 E+06 2.67E+06 2.59E+06 2.51 E+06 2.51 E+06 1.55E+07 2.68E+06 2.59E+06 2.27E+06 2.59E+06 2.38E+06 2.57E+06 3.05E+07 Total Gallons 9.55E+06 8.86E+06 1.02E+07 6.71 E+06 6.37E+06 9.69E+06 5.14E+07 9.60E+06 9.152+06 9.10O2+06 1.01E+07 9.91 E+06 1.04E+07 1.1OE+08 Total cc 3.61E+10 3.35E+10 3.85E+10 2.54E+10 2.41E+1 0 3.67E+10 1.94E+11 3.63E+10 3.46E+10 3.44E+10 3.82E+10 3.75E2+1 0 3.94E+10 4.15E+11 Vol of dilution water (cc)**

6.62E+13 6.20E+13 6.81 E+13 5.95E+13 6.43E+13 1.01E+14 4.17E+14 1.15E+14 1.15E+14 1.10E+14 1.11E+14 9.61 E+13 7.20E+13 1.04E+15 Avg diluted discharge conc (iC i/cc)

=

GammaScan(+Fe-55) 2.33E-11 2.87E-11 2.24E-11 4.69E-11 5.72E-11 8.97E-11 7.74E-12 3.17E-12 2.47E-12 2.30E-12 2.01E-12 5.51E-12 Gross Alpha 8.50E-15 1.40E-14 O.OOE+00 O.OOE+00 O.OOE+400 0.002+00 6.49E-15 O.OOE+00 O.OOE+OO O.OOE+00 3.07E-14 O.OOE+OO Tritium 2.97E-07 9.79E-07 6.94E-07 3.48E-07 1.45E-06 2.43E-07 1.07E-07 3.95E-07 1.24E-07 6.96E-07 1.38E-06 8.49E-07 Strontium (89/90/92) 0.002o+00 0.002+00 0.002+00 0.002+00 0.002+00 0.002+00 0.002+00 0.002+00 0.00+00 0.00O+00 0.002+00 0.002+00 Max Batch Discharge Cone (tt I/cc)'

Tritium 2.11E-05 1.85E-05 1.33E-05 7.622-06 4.19E-05 5.00E-06 5.04E-06 1.99E-05 6.26E-06 2.00-E05 2.01E-05 2.24E205 GammaScan(+Fe55)

Ji1.17E-09 8.84E210 3.73E-10 1.55E-09 1.38E-09 2.43E-09 I 1.302-10 1.83E-10 1.71E-10 3.17E-11 5.48E-11 9.25E-11 The Retention Pond was taken out of service in September 2002 and replaced with the waste water effluent filter system.

- Circulating water discharge from both units.

Note: The Dissolved noble gases detected in liquid effluents (e.g., Xe-133 and Xe-135) are added to the atmospheric release summaries.

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Table 2-3 Isotopic Composition of Circulating Water Discharges (CI)

January, 2004 through December 31, 2004 Total Total Nuclide Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Jan-Dec H-3 1.97E+01 6.06E+01 4.73E+01 2.07E+01 9.32E+01 2.46E+01 2.66E+02 1.23E+01 4.54E+01 1.37E+01 7.74E+01 1.32E+02 6.11E+01 6.08E+02 F-18 2.26E-04 2.31E-04 7.66E-05 1.85E-04 0.00E+00 5.85E-05 7.78E-04 2.06E-04 O.OOE+00 O.OOE+00 1.48E-04 5.66E-05 1.13E-04 1.30E-03 Cr-51 3.49E-05 O.OOE+00 O.OOE+00 1.22E-05 1.26E-04 2.52E-04 4.25E-04 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 4.25E-04 Mn-54 1.89E-05 2.02E-05 1.14E-05 1.16E-05 2.19E-05 1.86E-05 1.03E-04 1.19E-05 5.17E-06 O.OOE+00 O.OOE+00 1.74E-06 O.OOE+00 1.21E-04 Fe-55 1.67E-04 4.47E-04 3.58E-04 3.56E-04 1.06E-03 8.08E-04 3.20E-03 4.40E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.07E-04 3.85E-03 Fe-59 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 3.83E-05 1.78E-05 5.61 E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.61E-05 Co-57 O.OOE+00 O.OOE+00 8.63E-06 O.OOE+00 1.56E-06 4.38E-07 1.06E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 1.06E-05 Co-58 5-56E-04 5.63E-04 3.60E-04 9.27E-04 8.182-04 6.98E-04 3.922-03 4.28E-05 1.76W-05 1.04E-04 5.95E-06 1.68E-05 1.27E-05 4.12E-03 Co-60 1.88E-04 2.20E-04 1.992-04 1.89E-04 6.57E-04 2.15E-04 1.67E-03 1.66E-04 6.23E-05 1.32E-04 2.21E-05 4.10E-05 4.31E-05 2.13E-03 Zn-65 3.73E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.73E-06 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.73E-06 As-76 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 1.27E-05 O.OOE+00 1.27E-05 Sr-89 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00

.OOE+00 O.OOE+00 Nb-95 5.10E-05 2.95E-05 1.69E-05 3.13E-06 1.92E-05 5.37E-05 1.73E-04 O.OOE+00 0.00E+00 7.10E-06 O.OOE+00 2.56E-06 O.OOE+00 1.83E-04 Nb-97 O.OOE+00 O.OOE+00 O.OOE+00 2.39E-06 O.OOE+00 3.98E-06 6.38E-06 O.OOE+00 2.96E-06 O.OOE+00 O.OOE+00 3.53E-06 2.162-06 1.50E-05.

Zr-95 2.07E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.65E-06 2.722-05 5.26E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.26E Ag-l lOIm 7.46E-05 8.24E-05 2.73E-05 1.72E-05 6.902-05 1.85E-04 4.56E-04 9.02E-06 3.33E-05 2.85E-05 6.65E-06 7.12E-06 4.90E-06 5.45E-04 Sn-I 13 O.OOE+00 4.53E-06 2.72E-06 O.OOE+00 251E-05 O.OOE+00 3.23E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.23E-05 Sn-1 17m 2.44E-05 3.20E-05 2.80E-05 3.85E-05 1.59E-04 9.03E-04 1.19E-03 O.OOE+00 2.992-05 O.OOE+00 2.45E-05 4.09E-05 1.08E-05 1.29E-03 Sb-122 O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sb-124 2.60E-05 4.16E-05 1.12E-04 3.022-04 1.60E-04 1.1OE-03 1.74E-03 O.OOE+00 1.99E-05 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 1.762-03 Sb-125 5.90E-05 1.04E-04 3.21E-04 7.33E204 5.00-E04 4.71E-03 6.43E-03 1.48E205 1.91 04 O.OOE+00 4.82E-05 1.072-05 O.OOE+00 6.69E-03 1-131 O.OOE+00 O.OOE+00 2.50E06 O.OOE+00 O.OOE+00 O.OO2+00 2.50E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.ooe+00 0.00E+00 2.50E-06 Te-132 O.OOE+00 0.00E+00 O.OOE+00 1.07E-05 0.00E+00 O.OOE+00 1.07E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 1.07-E05 Cs-137 1.97E-06 4.89E-06 1.242-06 1.04E-06 1.62E-05 3.99E-06 2.93E-05 O.OOE+00 2.96E-06 O.OOE+00 O.OOE+00 O.OOE+00 3.41E-06 3.57E-05 Note: The dissolved noble gases detected in liquid effluents (e.g., Xe-133, Xe-135, etc.) are added to the atmospheric release summaries.

7

THIS PAGE PURPOSEFULLY LEFT BLANK 8

Table 2-4 Subsoil System Drains - Tritium Summary January 1, 2004, through December 31, 2004 S-1 S-3 S-7 S-8 S-9 S-1 0 1st Qtr H-3 (Ci)

O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 Flow (gal) 1.77E+06 1.92E+05 4.1 8E+04 O.OOE+OO O.OOE+00 4.18E+05 2nd Qtr H-3 (Ci)

O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+00 Flow (gal) 9.40E+05 2.64E+05 O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+00 3rd Qtr H-3 (Ci)

O.OOE+00 O.OOE+O0 O.OOE+0O O.OOE+00 O.OOE+O0 O.OOE+OO Flow (gal) 2.23E+05 1.32E+05 1.08E+04 O.OOE+00 O.OOE+O0 O.OOE+0O 4th Qtr H-3 (Ci)

O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+0C Flow (gal) 1.79E+05 2.79E+05Q O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+0C 2.6 Land Application of Sewage Sludge The Wisconsin Department of Natural Resources has approved the disposal of PBNP sewage by land application on various Wisconsin Electric Power Company properties surrounding PBNP. This sewage sludge, which may contain trace amounts of radionuclides, are to be applied in accordance with methodologies approved by the NRC on January 13, 1988, pursuant to 10 CFR 20.302(a). The approved methodology requires analyses prior to every disposal. Based upon an investigation of the source of the radionuclides, a combination of engineering modifications and administrative controls has eliminated plant generated radiological inputs to the sewage. This was verified by sludge analyses using the environmental lower level of detection (LID) criteria. No byproduct radionuclides were found in the sludge after the controls and modifications were completed. Sludge is routinely monitored and no radionuclides attributable to PBNP have been found.

There was no disposal of sewage by land application during 2004. All disposals were done at the Manitowoc Sewage Treatment Plant.

9

3.0 RADIOACTIVE AIRBORNE RELEASES The release paths to the environment contributing to radioactive airborne release totals during this reporting period were the Auxiliary Building Vent Stack, Drumming Area Vent Stack, Unit 1 Containment Purge Stack, and Unit 2 Containment Purge Stack. A gaseous radioactive effluent treatment system in conjunction with administrative controls is used to minimize the impact on the environment from the airborne releases and maintain doses to the public ALARA.

3.1 Doses From Airborne Effluent Doses from airborne effluent are calculated for the maximum exposed individual (MEI) following the methodology contained in the PBNP ODCM. These calculated doses use parameters such as the amount of radioactive material released, the concentration at and beyond the site boundary, the average site weather conditions, the locations of the exposure pathways (e.g., cow milk, vegetable gardens and residences), and usage factors (e.g., breathing rates, food consumption). In addition to the MEI doses, the energy deposited by beta particles and gamma rays in air is calculated and compared to the corresponding Appendix I design objectives. A comparison of the annual Appendix I design objectives for atmospheric effluents to the highest organ dose and the noble gas doses calculated using ODCM methodology is listed in Table 3-1. The doses demonstrate that releases from PBNP to the atmosphere continue to be ALARA.

3.2 Radioactive Airborne Release Summary Radioactivity released in airborne effluents for 2004 are summarized in Table 3-2.

3.3 Isotopic Airbome Releases The monthly isotopic airborne releases for 2004, from which the airborne doses were calculated, are presented in Table 3-3.

10

Table 3-1 Comparison of 2004 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Annual Appendix I Design January-December Percent of Appendix I Category Objective Calculated Dose Design Objective Particulate 30 mrem/organ 0.0238 mrem 7.93E-02 Noble gas 40 mrad (beta air) 0.0001 66 mrad 4.15E-04 Noble gas 20 mrad (gamma air) 0.000406mrad 2.03E-03 Noble gas 30 mrem/organ 0.000578 mrem 1.93E-03 Noble gas 10 mrem (whole body) 0.000386 mrem 3.86E-03 Table 3-2 Radioactive Airborne Effluent Release Summary January 1, 2004, through December 31, 2004

.Ja Rb Mr Air Miy Jun Jm Jul AP Nw Dx

_T__

'flbINGfitnUq(G) 3.5AN 6L380 1.MMM 1.51E 4.11IB 4.6O 25512 1-6B 8-5 (1MM 43110M 215i; 1.125tB 294802 TlbWN9ieC3W(Q)1 7.1(M 1.1M;01 1.201 121801 1.60I 7.77S0 634801

&1(

9.548 9.71 1.5401

&43 154801 1Q((

nW Rxicoffm (G) 0a0 0a0W13-HMO GOMM 1.ss8o7 aOOM 1 1.8s5o O.Mso a0013.0) wxr0.n aWo& (loom Gm3BM 1.8587 nd Prtkdate aaEM 12Mo 1.17Sa6 1.sB 1S

&91&12 aaA) aaoM GOM a00(oo m

aao 0M am;M aaE ao At (G) aOE. 0013.0 1010) ao.)

Q 0 )

(loom 001.0)M (m;a0 )

(

0 aQXE.+00 aaXEo GOMM 00113.)

Gomo untium(G)

HEMO GOMM 013 1.a4o 1a39 8.94&12 3283 00130a (amn aOoi.

aGoMO Q00.

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323 Al hs (Pnm) (cG) 0(I1am.

1.2.

1.17805 G(OMM.0 0(13.0)

GOG&M 1.17805 GX3i0 Q001 D 0 4 aOO0 HOMO aXE400 1.17B06 T11iTHMn(G) 7SM 4578.0 3,796 6.05.

6458a 3=30 2.+01 5670 36110) 2378.0) 690M 7.99.

6020 605Q.01 MT1cbXt1y1(v:)

9.0RA

1.

1.387 60306 WA87 20W7 1.37 1A3807 1.4Afi7 1.41807 I

I1A307 2107 1 'ducis nciegsaorition franlKiidrde;.

1 Total noble gas (airborne + liquid releases).

2 Total Particulate is the sum of alpha, strontium, and others. It does not include radioiodines.

TABLE 3-3 Isotopic Composition of Airborne Releases January 1, 2004 through December 31, 2004 Jan Feb Mar Apr May Jun Semi-Jul Aug Sep Oct Nov Dec Total Nuclide (Ci)

() (

(Ci)

Annual (Ci)

(Ci)

H-3 3.87E+00 4.57E+00 3.79E+00 6.05E+00 6.45E+00 3.22E+00 2.79E+01 5.67E+00 3.61E+00 2.37E+00 6.94E+00 7.99e+00 6.02e+00 6.05E+01 Ar-41 6.47E-02 851E-02 7.49E-02 4.55E-02 7.32E-02 6.28E-02 4.06E-01 6.28e-02 5.94E-02 5.01 E-02 8.13e-02 6.93E-02 I.18E-01 8.47E-01 Kr-85m 0.00e+00 1.04E-04 o.OOE+00 o.ooe+00o 1.98E-03 1.29E-04 2.21E-03 O.OOE+00 o.ooe+00 O.OOE+00 o.ooe+00 4.17E-05 5.86E-04 2.84E-03 Kr-87 O.OOE+00 2.58E-04 0.00e+00 O.OOE+00 5.ooe-03 3.34E-04 5.59E-03 0.OOB+00 o.ooe+00 o.ooe+00 o.ooe+00 1.02E-04 1.58E-03 7.272-03 Kr-88 o.ooe+00 2.52E-04 O.OOE+00 o.ooe+00 551E-03 3.51E-04 6.11 E-03 o.ooe+00 0.002+00 o.ooE+00 o.ooe+00 9.95E-05 1.41E-03 7.62E-03 Xe-133 6.27H-03 2.66E-02 4.80E-02 7.482-02 6.05E-04 9.42E-03 1.66E-01 1.76E-02 356E-02 4.65E-02 7.23E-02 1.37E-02 1.85E-02 3.702-01 Xe-133m O.OOE+00 1.07E-04 253E-04 1.772-04 o.ooe+00 O.OOE+00 5.37E-04 O.OOE+00 O.OOE+00 O.OOE+00 4.24E-04 6.88E-06 0.00E+00 9.67E-04 Xe-135 4.51E-05 8.36E-04 2s4E-04 5.13E-05 1.08E-02 2582-03 1.462-02 4.51E-04 4.302-4 5.77E-04 2.43E-04 3.37E-04 3.08E-03 1.97e-02 Xe-135m o.ooe+00 3.72E-04 0.00e+00 O.OOE+00 7.85E-03 5.922-04 8.812-03 1.36E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.91E-04 2.67E-03 1.182-02 Xe-138 o.ooe+00 1.242-03 o.ooe+00 o.ooe+00 2.14E-02 1.50E-03 2.41E-02 0.00o+00 o.ooe+00 o.ooe+00 0.002+00 5.25e-04 7.90e-03 3.2se-02 F-18 o.ooe+00 1.28E-10 1.17E-06 o.ooe+00 o.ooe+00 o.ooe+00 1.17E-06 o.oo00+00 0.OE+00 o.ooe+00 o.ooe+00 o.ooe+00 o.ooe+00 1.17E-06 1-131 o.ooe+00 o.ooe+00 o.ooe+00 o.ooe+00 1.85e-07 o.ooe+00 1.85E-0 0.002+00o o.ooe+00 o.ooe+00 o.ooe+00 o.ooe+00 o.ooe+00 1.85E-07 Sr-90 0.00e+00 0.00e+00o o.ooe+00 1.8381E-o0 1.39e-08 8.94E-12, 3.23E-8 o.ooe+00o o.ooe+00 O.OOE+00 o.ooe+00 o.ooe+00 0.00e+00 3.23E-08 Note: The Noble Gases listed above include the liquid contribution.

4.0 RADIOACTIVE SOLID WASTE SHIPMENTS 4.1 Types, Volumes, and Activity of Shipped Solid Waste The following types, volumes, and activity of solid waste were shipped from PBNP for offsite disposal or burial during 2004. No types C or D were shipped.

No irradiated fuel was shipped offsite. The volume, activity, and type of waste are listed in Table 4-1.

Table 4-1 Quantities and Types of Waste Shipped from PBNP Type of Waste Quantity Activity A. Spent resins, filter sludge, evaporator bottoms, etc.

18.12 m3 64.64 Ci 639.80 ft3 B. Dry compressible waste, contaminated equipment, etc 485.00 m3 0.6500 Ci 17131.50 ft3 C. Irradiated components, control rods, etc.

0.00m 3 N/A Ci 0.00 ft3 D. Other 0.00 m3 N/A Ci 0.00 ft3 4.2 Major Nuclide Composition (by Type of Waste)

The major radionuclide content of the solid waste was determined by gamma isotopic analysis and the application of scaling factors for certain indicator radionuclides based on the measured isotopic content of representative waste stream samples. The estimated isotopic content is presented in Table 4-2.

13

Table 4-2 2004 Estimated Solid Waste Major Radionuclide Composition TYPE A TYPE B TYPE C TYPE D l

Percent Percent Percent Percent Nuclide Abundance Nuclide Abundance Nuclide Abundance Nuclide Abundance Ni-63 50.41%

Co-60 32.41%

Fe-55 20.20%

Ni-63 26.03%

Co-58 14.30%

Fe-55 19.52%

Co-60 10.43%

0Co-58 11.04%

H-3 2.42%

Cs-137 4.46%

Sb-125 1.38%

Sb-1 25 1.55%

Ni-59 0.30%

Nb-95 1.41%

Cs-1 37 0.29%

Ag-i 10 1.26%

Ag-110 0.11%

H-3 1.15%

Tc-99 0.09%

C-1 4 0.28%

Nb-95 0.02%

Pu-241 0.24%

C-14 0.02%

Po-210 0.23%

Sr-90 0.01%

Ni-59 0.15% l Sr-90 0.08%

Nb-94 0.07%

Pu-238 0.04%

Am-241 0.04%

Pu-239 0.02%

Cm-243 0.01%_

14

4.3 Solid Waste Disposition There were 14 solid waste shipments from PBNP during 2004. The dates and destinations were:

Table 4-3 2004 PBNP Radioactive Waste Shipments Date Destination Date Destination 01/20/04 Erwin, TN 01/27/04 Wampum, PA 03/09/04 Wampum, PA 03/31/04 Memphis, TN 04/08/04 Oak Ridge, TN 04/14/04 Memphis, TN 04/21/04 Memphis, TN 05/05/04 Memphis, TN 05/11/04 Memphis, TN 05/27/04 Oak Ridge, TN 07/22/04 Wampum, PA 08/18/04 Memphis, TN 09/14/04 Wampum, PA 12/20/04 Memphis, TN 15

5.0 NONRADIOACTIVE CHEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system from January 1, 2004, to June 30,2004, included 6.32E+05 gallons of neutralized wastewater. The wastewater contained 7.71E+00 pounds of suspended solids and 5.26E+03 pounds of dissolved solids.

Scheduled chemical waste releases to the circulating water system from July 1, 2004, to December 31, 2004, included 5.85E+05 gallons of neutralized wastewater. The wastewater contained 3.01E+01 pounds of suspended solids and 5.61E+03 pounds of dissolved solids.

Scheduled chemical waste releases are based on the average analytical results obtained from sampling a representative number of neutralizing tanks.

5.2 Miscellaneous Chemical Waste Releases Miscellaneous chemical waste releases from the Wastewater Effluent (based on effluent analyses) to the circulating water for January 1, 2004, to June 30, 2004, included 2.44E+07 gallons of clarified wastewater. The wastewater contained 2.93E+03 pounds of suspended solids.

Miscellaneous chemical waste releases from the Wastewater Effluent (based on effluent analyses) to the circulating water for July 1, 2004, to December 31, 2004, included 2.74E+07 gallons of clarified wastewater. The wastewater contained 3.81E+03 pounds of suspended solids.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1, 2004, to June 30, 2004, included 9.54E+04 pounds of sodium bisulfite and 2.46E+04 pounds of sodium hypochlorite.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1, 2004, to December 31, 2004, included 1.38E+05 pounds of sodium bisulfite and 3.12E+04 pounds of sodium hypochlorite.

16

6.0 CIRCULATING WATER SYSTEM OPERATION The circulating water system operation during this reporting period for periods of plant operation is described in Table 6-1.

Table 6-1 Circulating Water System Operation for 2004 l UNIT JAN FEB MAR APR MAY JUN Average Volume Cooling 1

282.2 282.2 282.9 231.6 254.4 400.9 Water Discharge [million galdayl**

2 282.2 282.2 297.9 492.3 466.1 491.9 Average Cooling Water 1

37 37 38 41 48 50 Intake Temperature [FF]

2 37 37 38 44 48 50 Average Cooling Water 1

69 69 70 56*

49*

64*

Discharge Temperature ["F]

2 72 72 71 64 66 70 Average Ambient Lake Temperature [°F]

39 41 44 50 54 55

Unit 1 shutdown from Apr 3 - June 7,2004.

- For days with cooling water discharge flow.

Table 6-1(continued)

Circulating Water System Operation for 2004 l UNIT JUL AUG SEP OCT NOV DEC Average Volume Cooling 1

489.6 489.6 486.1 490.4 489.2 306.5 Water Discharge [million gal/day]**

2 489.6 489.6 486.1 457.4 357.1 306.2 Average Cooling Water 1

60 58 57 51 46 38 Intake Temperature ["F]

2 60 56 55 51 46 38 Average Cooling Water 1

80 76 74 71 66 68 Discharge Temperature ["F]

2 80 76 75 71 69 70 Average Ambient Lake Temperature [F]

A 66 61 60 57 52 44

- For days with cooling water discharge flow.

17

Part B IMiscellaneous Reporting Requirements 7.0 ADDITIONAL REPORTING REQUIREMENTS 7.1 Revisions to the PBNP Effluent and Environmental Programs The PBNP Offsite Dose Calculation Manual was revised during 2004.

Editorial changes to the ODCM consisted of redefining program responsibilities, correcting labels on a figure, clarifying alarm setpoint guidelines, and correcting a typo.

A complete copy is included with this AMR submittal.

7.2 Interlaboratory Comparison Program Environmental, Inc, Midwest Laboratory, the analytical laboratory contracted to perform the radioanalyses of the PBNP environmental samples, participated in the interlaboratory comparison studies administered by Environmental Resources Associates during 2004. Environmental, Inc., Midwest Laboratory also participated in the Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP) and the Environmental Measurements Laboratory (EML) Quality Assessment Program. The results of these comparisons can be found in Appendix A of the AMR.

7.3 Special Circumstances No special circumstances report regarding operation of the explosive gas monitor for the waste gas holdup system was needed during 2004.

18

l Part C RADIOLOGICAL ENVIRONMENTAL MONITORING

8.0 INTRODUCTION

The objective of the PBNP Radiological Environmental Monitoring Program (REMP) is to determine whether the operation of PBNP or the ISFSI has radiologically impacted the environment. To this end, the REMP collects and analyzes air, water, milk, soil, vegetation, and fish samples for radionuclides and uses TLDs to determine the ambient radiation background. These measurements also serve as a check of the efficacy of PBNP effluent controls. The REMP fulfills the requirements of 10 CFR 20.1302, PBNP General Design Criterion (GDC) 17, GDC 64 of Appendix A to 10 CFR 50, and Sections IV.B.2 and IV.B.3 of Appendix I to 10 CFR 50 for the operation of the plant. Therefore, the REMP collects samples from various environmental media in order to provide data on measurable levels of radiation and radioactive materials in the principal pathways of environmental exposure.

A subset of the PBNP REMP samples, consisting of air, soil, and vegetation, also fulfills 10 CFR 72.44(d)(2) for operation of the ISFSI. Additionally, thermoluminescent dosimeters (TLDs) provide the means to measure changes in the ambient environmental radiation levels at sites near the ISFSI and at the PBNP site boundary to ensure that radiation levels from the ISFSI are maintained within the dose limits of 10 CFR 72.104.

Because the ISFSI is within the PBNP site boundary, radiation doses from PBNP and the ISFSI, combined, must be used to assess compliance with 10 CFR 72.122 and 40 CFR 190.

Therefore, radiological environmental monitoring for the ISFSI is provided by selected sampling sites, which are part of the PBNP REMP.

For the aquatic environment, the samples include water as well as the biological integrators, such as fish and filamentous algae. Because of their migratory behavior, fish are wide area integrators. In contrast, the filamentous algae periphyton is attached to shoreline rocks and concentrate nuclides from the water flowing by their point of attachment. Grab samples of lake water provide a snapshot of radionuclide concentrations at the time the sample is taken; where as analysis of fish and filamentous algae yield concentrations over time.

The air-grass-cow-milk exposure pathway unites the terrestrial and atmospheric environments. This pathway is important because of the many dairy farms around PBNP.

Therefore, the REMP includes samples of air, general grasses, and milk from the PBNP environs. An annual land use survey is made to determine whether the assumptions on the location of dairy cattle remain conservative with respect to dose calculations for PBNP effluents. The dose calculations assume that the dairy cattle are located at the south site boundary, the highest depositional sector. In addition, soil samples are 19

collected and analyzed in order to monitor the potential for long-term buildup of radionuclides in the vicinity of PBNP.

For the measurement of ambient environmental radiation levels that may be affected by direct radiation from PBNP or by noble gas effluents, the REMP employs a series of TLDs situated around PBNP and the ISFSI.

9.0 PROGRAM DESCRIPTION 9.1 Results Reporting Convention The vendor used by PBNP to analyze the environmental samples is directed to report analysis results as measured by a detector, which can meet the required lower level of detection (LLD) as specified in Table 2-2 of the Environmental Manual for each sample. The report provided by the vendor (see the Appendix) contains values, which can be either negative, positive or zero plus/minus the two sigma counting uncertainty, which provides the 95% confidence level for the measured value.

The lower limit of detection (LLD) is an a priori concentration value that specifies the performance capability of the counting system used in the analyses of the REMP samples. The parameters for the a priori LLD are chosen such that only a five percent chance exists of falsely concluding a specific radionuclide is present when it is not present at the specified LLD. Based on detector efficiency and average background activity, the time needed to count the sample in order to achieve the desired LLD depends upon the sample size. Hence, the desired LLD may be achieved by adjusting various parameters. When a suite of radionuclides are required to be quantified in an environmental sample such as lake water, the count time used is that required to achieve the LLD for the radionuclide with the longest counting time. Therefore, in fulfilling the requirement for the most difficult to achieve radionuclide LLD, the probability of detecting the other radionuclides is increased because the counting time used is longer than that required to achieve the remaining radionuclide LLDs.

The REMP results in this report are reported as averages of the measurements made throughout the calendar year plus/minus the associated standard deviation.

If all net sample concentrations are equal to or less than zero, the result is reported as "Not Detectable" (ND), indicating no detectable level of activity present in the sample. If any of the net sample concentrations indicate a positive result statistically greater than zero, all of the data reported are used to generate the reported statistics. Because of the statistical nature of radioactive decay, when the radionuclide of interest is not present in the sample, negative and positive results centered about zero will be seen. Excluding validly measured concentrations, whether negative or as small positive values below the LLD, artificially inflates the calculated average value. Therefore, all generated data are 20

used to calculate, when applicable, the statistical parameters (i.e., average, standard deviation) presented in this report. Negative averages are reported as ND.

In interpreting the data, effects due to the plant must be distinguished from those due to other sources. A key interpretive aid in assessment of these effects is the design of the PBNP REMP, which is based upon the indicator-control concept.

Most types of samples are collected at both indicator locations (e.g., nearby, downwind, or down stream) and at control locations (e.g., distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuation in radiation levels arising from other sources.

9.2 Sampling Parameters Samples are collected and analyzed at the frequency indicated in Table 9-1 from the locations described in Table 9-2 and shown in Figures 9-1, 9-2, and 9-3. (The latter two figures show sampling locations not shown in preceding figures due to space limitations. The location of the former retention pond is indicated in Fig. 9-3). The PBNP REMP sampling sites used to determine environmental impact around the ISFSI are found in Table 9-3. The minimum acceptable sample size is found in Table 9-4. In addition, Table 9-1 indicates the collection and analysis frequency of the ISFSI fence TLDs.

9.3 Deviations from Required Collection Frequency Deviations from the collection frequency given in Table 9-1 are allowed because of hazardous conditions, automatic sampler malfunction, seasonal unavailability, and other legitimate reasons (Section 2.2.6 of the Environmental Manual). Table 9-5 lists deviations from the scheduled sampling and frequency, which occurred during the reporting period.

9.4 Assistance to the State of Wisconsin The Radiation Protection Unit of the Wisconsin Department of Health and Family Services maintains a radiological environmental monitoring program in order to confirm the results from the PBNP REMP. As a courtesy to the State of Wisconsin, PBNP personnel also collect certain environmental samples (Table 9-

6) for the State from sites, which are near PBNP sampling sites or are co-located.

The results of the State monitoring program are available from the Radiation Protection Unit of the Wisconsin Department of Health and Family Services.

9.5 Program Modifications No program modifications were made during 2004.

21

Table 9-1 PBNP REMP Sample Analysis and Frequency Sample Type Sample Codes Analyses Frequency Environmental Radiation E-01, -02, -03, -04, -05 D

Quarterly Exposure 06, -07, -08, -09, -12 14, -15, -16, -17, -18, 20, -22, -23, -24, -25, 26, -27, -28, -29, -30,

-31, -32, -38, -39, -TC Vegetation E-01, -02, -03, -04, -06, Gross Beta 3x/yr as available

-08, -09, -20, Gamma Isotopic Analysis Algae E-05, -12 Gross Beta 3x/yr as available Gamma Isotopic Analysis Fish E-13 Gross Beta 3x/yr as available Gamma Isotopic Analysis (Analysis of edible portions only)

Well Water E-10 Gross Beta, H-3 Quarterly Sr-89, 90, I-131 Gamma Isotopic Analysis (on total solids)

Lake Water E-01, -05, -06, -33 Gross Beta Monthly / Quarterly composite of monthly collections I-131 Monthly amma Isotopic Analysis onthly (on total solids)

Milk E-11, -40, -21 Sr-89,90 Monthly I-131 Gamma Isotopic Analysis ir Filters E-01, -02, -03, -04, Gross Beta Wekly (particulate) 08, -20 1-131 eekly (charcoal)

Gamma Isotopic Analysis Quarterly (on composite particulate filters)

Soil E-01, -02, -03, -04, oss Beta 2x/yr

-06, -08, -09. -20, amma Isotopic Analysis Shoreline Sediment E-01, -05, -06, -12, -33, oss Beta 2x/yr Gamma Isotopic Analysis ISFSI Ambient Radiation orth, East, South, West Quarterly Exposure Fence Sections I

22

Table 9-2 PBNP REMP Sampling Locations Location Code Location Description E-01 Primary Meteorological Tower South of the Plant E-02 Site Boundary Control Center - East Side of Building E-03 Tapawingo Road, about 0.4 Miles West of Lakeshore Road E-04 North Boundary E-05 Two Creeks Park E-06 Point Beach State Park - Coast Guard Station; TLD located South of the Lighthouse on Telephone pole E-07 WPSC Substation on County V, about 0.5 Miles West of Hwy 42 E-08 G.J. Francar Property at Southeast Corner of the Intersection of Cty. B and Zander Road E-09 Nature Conservancy E-10 PBNP Site Well E-11 Dairy Farm about 3.75 Miles West of Site E-12 Discharge Flume/Pier E-13 Pumphouse E-14 South Boundary, about 0.2 miles East of Site Boundary Control Center E-15 Southwest Corner of Site E-16 WSW. Hwy 42, a residence about 0.25 miles North of Nuclear Road E-17 North of Mishicot, Cty. B and Assman Road, Northeast Corner of Intersection E-18 Northwest of Two Creeks at Zander and Tannery Roads E-40 Local Dairy Farm, W side of Hwy 42. about 1.8 miles north of the Nuclear Rd intersection E-20 Reference Location, 17 miles Southwest, at Silver Lake College E-21 Local Dairy Farm just South of Site on Lakeshore and Irish Roads E-22 West Side of Hwy 42, about 0.25 miles North of Johanek Road E-23 Greenfield Lane, about 4.5 Miles South of Site, 0.5 Miles East of Hwy 42 E-24 North Side of County Rt. V. near intersection of Saxonburg Road E-25 South Side of County Rt. BB, about 0.5 miles West of Norman Road E-26 804 Tapawingo Road, about 0.4 miles East of Cty. B, North Side of Road E-27 Intersection of Saxonburg and Nuclear Roads, Southwest Corner, about 4 Miles WSW E-28 TLD site on western most pole between the 2d and 3d parking lots.

E-29 Area of North Meteorological Tower.

E-30 NE corner at Intersection of Tapawingo and Lakeshore Roads.

E-31 On utility pole North side of Tapawingo Road closest to the gate at the West property line.

E-32 On a tree located at the junction of property lines, as indicated by trees and shrubs, about 500 feet east of the west gate on Tapawingo Road and about 1200 feet south of Tapawingo Road. The location is almost under the power lines between the blue and gray transmission towers.

E-33 Lake Michigan shoreline accessed from the SE corner of KNPP parking lot. Sample South of creek.

E-38 Tree located at the West end of the area previously containing the Retention Pond.

E-39 Tree located at the East end of the area previously containing the Retention Pond.

E-TC Transportation Control; Reserved for TLDs 23

M41 57 POINT BEACH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SITES o

1

-MILE r"1----

r--7 KILOMETER Figure 9-1 PBNP REMP Sampling Sites 24

SI TE MAP POINT BEACH NUCLEAR PLANT Flatc 2-1b ENVIRONMENTAL MONITORING STATIONS 0

TLD

@ ULD & AIR A& OTHER eMs FILE 107 Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 25

FIOUK 2-IC Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 26

Table 9-3 ISFSI Sampling Sites Ambient Radiation Monitoring (TLD)

Soil, Vegetation, and Airborne Monitoring E-03 E-02 E-28 E-03 E-30 E-04 E-31 II E-32 I

Table 9-4 Minimum Acceptable Sample Size Sample Type Size Vegetation 100-1000 grams Lake Water 8 liters Air Filters 250 m3 (volume of air)

Well Water 8 liters Milk 8 liters Algae 100-1000 grams Fish (edible portions) 1000 grams Soil 500-1000 grams Shoreline Sediment 500-1000 grams 27

Table 9-5 Deviations from Scheduled Sampling and Frequency Sample Location Collection Reason for not conducting Plans for Preventing Recurrence

.TypeDate REMP as required LW E-01, 2/15/2004 Sample unavailable due to Ice conditions are not controlable. Samples missed E-05, ice.

due to environmental conditions are expected and E-06, is so noted in Section 2.2.6 of the Environmental E-33 Manual.

AP/Al E-02 3/10/2004 Sample unavailable due to Power loss at E-02 continues from 2002.

E-04 7/28/2004 loss of power to the pump Evaluations continue to determine the cause(s) so The sampling volume could that corrections can be made. Power failure at E-04 not be quantified.

28

Table 9-6 Sample Collections for State of Wisconsin Sample Type Location Frequency Lake Water E-O1 Weekly, Composited Monthly Air Filters E-07 Weekly E-08 Fish E-13 Quarterly, As Available Precipitation E-04 Twice a month, E-08 As Available Milk E-11 Monthly E-19 Well Water E-10 Twice per year 29

9.6 Analytical Parameters The types of analyses and their frequencies are given in Table 9-1. The LLDs for the various analyses are found in the Section 10 (Table 10-1) with the summary of the REMP results. All environmental LLDs listed in Table 2-2 of the Environmental Manual (also in Table 10-1) were achieved during 2004.

9.7 Brief Description of Analytical Parameters in Table 9-1 9.7.1 Gamma isotopic analysis Gamma isotopic analysis consists of a computerized scan of the gamma ray spectrum from 80 keV to 2048 keV. Specifically included in the scan are Mn-54, Fe-59, Co-58, Co-60, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. However, any other nuclear power plant produced radionuclides, which are detected, also are noted. Naturally occurring radionuclides such as Ra-226, Bi-214, Pb-212, Tl-208, Ac-228, Be-7, and K-40 are frequently detected in soil, sediment, and vegetation but are not normally reported in this Annual Monitoring Report. All other radionuclides detected by gamma isotopic analysis are decay corrected to the time of collection.

9.7.2 Gross Beta Analysis Gross beta analysis is a non-specific analysis that consists of measuring the total beta activity of the sample. No individual radionuclides are identifiable by this method. Gross beta analysis is a quick method of surveying samples for the presence of elevated activity that may require additional, immediate analyses.

9.7.3 Water Samples Water samples include both Lake Michigan and well water. The Lake Michigan samples are collected along the shoreline at two locations north and two locations south of PBNP. The well water is sampled from the on-site PBNP well. Gross beta and gamma isotopic analytical results for water are obtained by measurements on the solids remaining after evaporation of the unfiltered sample to dryness. Hence, the results are indicated as "on total solids" in Table 10-1.

9.7.4 Air Samples Particulate air filters are allowed to decay at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before gross beta measurements are made in order for naturally occurring radionuclides to become negligible part of the total activity. Gross beta measurements 30

serve as a quick check for any unexpected activity that may require immediate investigation. Quarterly composites of the particulate air filters are analyzed for long-lived radionuclides such as Cs-134 and Cs-137. Charcoal filters are counted as soon as possible so the 1-131 will undergo only minimal decay prior to analyses.

In order to ensure that the air sampling pumps are operating satisfactorily, a gross leak check is performed weekly. The pumps are changed out annually for calibration and maintenance beyond what can be accomplished in the field.

9.7.5 Vegetation Vegetation samples consist predominantly of green, growing plant material (grasses and weeds most likely to be eaten by cattle if they were present at the sampling site). Care is taken not to include any dirt associated with roots by cutting the vegetation off above the soil line.

9.7.6 Environmental Radiation Exposure Environmental radiation exposure measurements taken in 2004 were performed with thermoluminescent dosimeter (TLD) cards. The TLDs absorb the energy deposited in them by gamma rays. The TLD card is a small passive detector, which integrates exposure through the use of a crystalline phosphorus material, calcium sulfate containing dysprosium.

Each TLD consists of a single Teflon sheet coated with calcium sulfate, which is read in four distinct areas to yield four values of exposure. This dosimeter design provides exposure information by averaging the four measured values. Prior to the third quarter of 2001, previous years' data were collected with TLDs that consisted of three lithium fluoride chips sealed in black plastic. The difference in material types can impact the amount of exposure measured. As seen in the 2001, the Environmental Inc. TLD cards typically produce a slightly higher measured exposure value, although within the uncertainty of that value recorded by the TLD chips.

The reported field exposure is the arithmetic average of the four exposure values obtained minus the exposure received while the field TLD is in storage and transit.

The gamma rays may originate from PBNP produced radionuclides or from naturally occurring radionuclides. The TLDs remain at the monitoring site for roughly three months prior to analyses and the results are reported as mrem per seven days. Because the TLDs are constantly bombarded by naturally occurring gamma radiation, even during shipment 31

to and from PBNP, the amount of exposure during transportation is measured using transportation controls with each shipment of TLDs to and from the laboratory. The doses recorded on the transportation controls are subtracted from the monitoring TLDs in order to obtain the net in situ dose.

9.7.7 ISFSI Ambient Radiation Exposure Although the ISFSI fence TLDs are not considered part of the REMP because of their location directly on site, their results can be used indirectly to determine whether the operation of the ISFSI is having an impact on the ambient environmental radiation beyond the site boundary.

Impacts are determined by comparison of fence TLD results to the results of the monitoring at PBNP site boundary and other selected locations.

10.0 RESULTS Summary of 2004 REMP Results Radiological environmental monitoring conducted at PBNP from January 1, 2004, through December 31, 2004, consisted of analysis of air filters, milk, lake water, well water, soil, fish, shoreline sediments, algae, and vegetation as well as TLDs. The results are summarized in Table 10-1.

Table 10-1 contains the following information:

Sample:

Type of the sample medium

==

Description:==

Type of measurement LLD:

a priori lower limit of detection N:

Number of samples analyzed Average:

Average value + the standard deviation of N samples High:

Highest measured value +/- its associated 2 sigma counting error Units:

Units of measurement Table 10-2 contains the ISFSI fence TLD results.

For certain analyses, an LLD which is lower than that required by REMP is used because the lower value derives from the counting time required to obtain the LLDs for radionuclides that are more difficult to detect. For these analyses, both LLDs are listed with the REMP LLD given in parentheses. The results are discussed in the narrative portion of this report (Section 11). Blank values have not been subtracted from the results presented in Table 10-1. A complete listing of all the individual results obtained from the contracted analytical laboratory and the laboratory's radioanalytical quality assurance results and Interlaboratory Crosscheck Program results are presented in the Appendix.

32

Table 10-1 Summary of Radiological Environmental Monitoring Results for 2004 Average t Standard Sample Description N

LLD (a)

Deviation (b)

High + 2 sigma Units TLD Environmental Radiation 112 1 mrem 1.10 + 0.22 1.68 + 0.1 rnR/7days Control (E-20) 4 1

mremr 1.06 +/- 0.14 1.19 +/- 0.12 mR17days Air Gross Beta 258 0.01 0.021 +/- 0.008 0.045 +/- 0.005 pCi/m3 Control (E-20) Gross beta 52 0.01 0.022 + 0.008 0.043 +/- 0.004 pCi/m3 1-131 258 0.030(0.07) 0.0005 +/- 0.0070 0.018 +/- 0.007 pCilm3 Control (E-20) 1-131 52 0.030 (0.07) 0.0007 +/- 0.0075 0.017 +/- 0.007 pCi/m3 Cs-134 24 0.05 0.0003 + 0.0003 0.0009 +/- 0.0006 pCi/m3 Cs-137 24 0.06 0.0002 +/- 0.0004 0.0007 +/- 0.0006 pCi/m3 Other gamma emitters 24 0.1 0.0001 +/- 0.0005 0.0014 :t 0.0009 pCi/m3 Milk Sr-89 36 5

ND pCi/L Sr-90 36 1

1.1 +/- 0.4 2.1 + 0.6 pCilL I-131 36 0.5 ND pCi/L Cs-134 36 5 (15) 0.6 +/- 1.3 2.7 +/- 2.3 pCilL Cs-137 36 5 (15) 0.9 +/- 1.7 5.5 + 2.1 pCi/L Ba-La-140 36 5 (15)

ND pCilL Other gamma emitters 36 15 0.4 +/- 1.2 2.8 + 2.5 pCilL W ell Gross beta 3

4 7.0 +/- 8.4 16.5 +/- 2.2 pCilL W ater H-3 3

500(3000) 36.3 +/- 65 110.8 + 88.9 pCilL Sr-89 3

10 ND pCilL Sr-90 3

1 (2)

ND pCilL I-131 3

0.5 (2)

ND pCilL Mn-54 3

10 (15)

ND pCilL Fe-59 3

30 ND pCilL Co-58 3

15 ND pCilL Co-60 3

15 ND pCilL Zn-65 3

30 ND pCilL Zr-Nb-95 3

15 ND pCilL Cs-134 3

15 ND pCi/L Cs-137 3

18 ND pCilL Ba-La-140 3

15 ND pCilL Other gamma emitters 3

30 ND pCilL Algae Gross beta 6

0.25 4.43 +/- 1.14 5.15 + 0.91 pCi/g Co-58 6

0.25 0.015 +/- 0.014 0.021 + 0.017 pCi/g Co-60 6

0.25 0.006 + 0.013 0.027 +/- 0.024 pCi/g

_____Cs-134 6

0.25 ND pCi/g Cs-137 6

0.25 0.018 +/- 0.007 0.024 + 0.016 pCi/g (a) The required LLD per the PBNP REMP is enclosed in the parentheses.

(b) "ND" indicates that the sample result is Not Detectable, i.e., sample concentrations were statistically equivalent to zero.

33

Table 10-1 (continued)

Summary of Radiological Environmental Monitoring Results for 2004 Average + Standard Sample Description N

LLD (a)

Deviation (b)

High + 2 sigma Units Lake Water Gross beta 44 4

2.8 + 1.0 7.3 + 0.8 pCi/L 1-131 44 0.5 (2)

ND pCi/L Mn-54 44 10 (15) 0.4 +/- 1.5 3.9 + 3.3 pCi/L Fe-59 44 30 ND pCi/L Co-58 44 15 ND pCi/L Co-60 44 15 0.3 +/- 1.4 2.7 +/- 2.3 pCi/L

=

Zn-65 44 30 N

ND pCi/L Zr-Nb-95 44 15 0.2 + 1.6 3.2 +/- 3 pCiIL Cs-134 44 10 (15) 0.1 +/- 1.7 2.8 +/- 2.4 pCi/L Cs-137 44 10(18) 0.1 +/- 1.2 1.8 +/- 1.3 pCi/L Ba-La-140 44 15 ND pCi/L Ru-103 (Other gamma) 44 30 ND pCi/L Sr-89 16 5

ND pCi/L Sr-90 16 1 (2) 0.61 + 0.26 1.12 + 0.62 pCi/L H-3 16 500(3000) 187 +/- 273 1186 +/- 126 pCiIL Fish Gross beta 10 0.5 3.63 +/- 0.99 5.77 +/- 0.13 pCi/g Mn-54 10 0.13 0.004 +/- 0.005 0.007 +/- 0.005 pCi/g Fe-59 10 0.26 0.009 +/- 0.022 0.032 +/- 0.028 pCi/g Co-58 10 0.13 ND pCi/g Co-60 10 0.13 ND pCi/g Zn-65 10 0.26 ND pCi/g Cs-134 10 0.13 ND pCi/g Cs-137 10 0.15 0.044 +/- 0.020 0.074 + 0.026 pCi/g Other gamma emitters 10 0.5 ND pCi/g Shoreline Gross beta 10 2

9.01 +/- 1.94 12.15 +/- 1.45 pCi/g Sediment Cs-137 10 0.15 0.022 +/- 0.014 0.058 + 0.021 pCi/g Soil Gross beta 16 2

24.31 +/- 5.47 31.25 2.89 pCi/g Cs-137 16 0.15 0.14 +/- 0.1 0.43 +/- 0.05 pCi/g Vegetation Gross beta 24 0.25 5.65 +/- 1.22 8.25 + 0.20 pCi/g I-131 24 0.06 0.000 +/- 0.001 0.020 +/- 0.009 pCi/g Cs-134 24 0.06 0.000 +/- 0.007 0.010 +/- 0.008 pCi/g Cs-137 24 0.08 0.005 +/- 0.009 0.020 +/- 0.014 pCi/g Other gamma emitters 24 0.06 0.003 + 0.007 0.0351+/- 0.017 pCi/g (a) The required LLD per the PBNP REMP is enclosed in the parentheses.

(b) "ND" indicates that the sample result is Not Detectable, i.e., sample concentrations were statistically equal to zero.

34

Table 10-2 ISFSI Fence TLD Results for 2004 Fence Location Average :+/- Standard Deviation North 2.61 +/- 0.16 mRI7 days East 2.12 +/- 0.11 mR/7 days South 1.41 +/- 0.06 mR17 days West 6.50 +/- 0.39 mR/7 days 11.0 DISCUSSION 11.1 TLD Cards The ambient radiation was measured in the general area of the site boundary, at an outer ring four - five miles from the plant, at special interest areas, and at one control location, roughly 17 miles Southwest of the plant. The average of the indicator TLD cards is 1.10 mR/7-days and 1.06 mR/7-days at the control location. These results are not significantly different from each other nor from those observed from 1993 through 2003 (tabulated below in Table 11-1). A change in TLD types accounts for the increase in average TLD readings (i.e., prior to third quarter 2001 TLD chips were used versus the TLD cards - see section 9.7.6 for additional information). Therefore, the operation of the plant has had no effect on the ambient gamma radiation.

Table 11-1 Average Indicator TLD Results from 1993 - 2003 Year Average

+/- St. Dev*

Units 1993 0.82 i

0.15 mR/7 days 1994 0.90 i

0.12 mR/7 days 1995 0.87

+/-

0.13 mR/7 days 1996 0.85

+

0.12 mR/7 days 1997 0.87

+/-

0.11 mR/7 days 1998 0.79 0.13 mR/7 days 1999 0.79 i

0.21 mR/7 days 2000 0.91

+/-

0.15 mRI7 days 2001 1.06

+/-

0.19 mR/7 days 2002 1.17

+/-

0.21 mR/7 days 2003 1.10 i

0.20 mR/7 days

St. Dev = Standard Deviation The annual ISFSI fence TLD results listed in Table 11-2 show the anticipated slow trend upward due to the cask additions each year (one added in January, one in December 2002, one in December 2003, and four in 2004). The North and 35

West fence TLDs continue to record higher doses than the South and East fence TLDs (see Table 11-2) corresponding to the location of the storage units at the NW comer of the site. Compared to the background site (E-20), most of the indicator sites for the ISFSI (Table 11-3) show increases within the expected statistical variation. Compared to the results at the background site, E-20, only a minimal increase in ambient gamma radiation at or beyond the site boundary due to the operation of the ISFSI is indicated.

Table 11-2 Average ISFSI Fence TLD Results (mR/7 days)

Sampling Site North East South West 1995 1.29 1.28 1.10 1.26 1996 2.12 1.39 1.10 1.68 1997 2.05 1.28 1.00 1.66 1998 2.08 1.37 1.02 1.86 1999 2.57 1.84 1.11 3.26 2000 2.72 2.28 1.25 5.05 2001 2.78 2.54 1.36 6.08 2002 2.79 2.74 1.42 6.46 2003 2.70 2.60 1.50 6.88 2004 2.61 2.12 1.41 6.50 Table 11-3 Average TLD Results Surrounding the ISFSI (mR/7 days)

E-03 E-28 E-30 E-31** E-32** E-20---

Pre-Operation*

0.93 0.87 0.81 0.93 0.98 0.88 1996 0.87 0.78 0.79 0.93 1.00 0.78 1997 0.91 0.89 0.84 0.89 0.97 0.79 1998 0.82 0.68 0.82 0.91 0.85 0.77 1999' 0.88 0.83 0.80 0.90 0.99 0.78 2000 0.98 0.88 0.99 0.98 1.06 0.90 2001 1.31 0.95 1.02 1.10 1.04 1.03 2002 1.45 0.91 1.10 1.26 1.25 1.14 2003 1.29 0.82 1.02 1.20 1.15 0.99 2004 1.35 0.80 1.05 1.23 1.18 1.06

Pre-Operation data is the averages of the years 2/92 through 3195.

- Sites E-31 and E-32 are located at the Site Boundary to the West and South-West of the ISFSI, respectively.

- - E-20 is located approximately 17 miles WSW of the ISFSI.

36

11.2 Milk Except for Sr-90, the annual average radionuclide concentrations in milk continue to be statistically not different from zero. The few statistically positive, individual monthly results for Ba/La-140 (6 of 36), Cs-134 (5 of 36), and Cs-137 (8 of 36) are attributed to statistical variations in the analyses of radioactive materials because PBNP did not emit any of these radionuclides to the atmosphere in 2004.

by. The Sr-90 concentrations result from the cycling of this radionuclide in the biosphere after the large-scale atmospheric weapons tests of the '50s, '60s, and

'70s and the Chernobyl accident. Although these test also introduced Cs-137 into the environment, Cs-137 binds more strongly to soils and therefore less likely to get into cows and milk. Although minute amounts of Sr-90 were emitted by PBNP in 2004 (see Table 3-3), the 2004 Sr-90 average (1.1 +/- 0.4 pCi/l) is identical to previous years: 1.1 + 0.4 in 2003, 1.1 + 0.7 in 2002, 1.2 +/- 0.5 in 2001, 1.2 +/- 0.6 in 2000, pCiAL, 1.0 +/-F 0.3 in 1999, 1.1 +/-t 0.5 in 1998, and 1.2 +/- 0.5 in 1997. These results are common throughout the Great Lakes region and North America. Therefore, it is concluded that the milk data for 2004 show no radiological effects of the plant operation.

11.3 Air The average annual gross beta concentrations (plus/minus the one-sigma uncertainty) in weekly airborne particulates at the indicator and control locations were 0.021 +/- 0.008 pCi/m3 and 0.022 +/- 0.008 pCi/m 3, respectively, and are similar to levels observed from 1993 through 2003 (Table 11-4).

Table 11-4 Average Gross Beta Measurements in Air Year Average (pCi/mi) l 1993 0.022 1994 0.022 1995 0.021 1996 0.021 1997 0.021 1998 0.022 1999 0.024 2000 0.022 2001 0.023 2002 0.023 2003 0.023 2004 0.021 37

Examination of the gross beta concentration variation over the year reveals higher concentrations in the Fall and Winter as compared to the Spring and Summer (Figure 1 1-1). This annual pattern is found throughout the region and is indicative of the different air masses and environmental conditions during the year which contribute long-lived, naturally-occurring radionuclides.

Figure 11-1 2004 Airborne Gross Beta Concentration (pCi/M3) vs. Time 0.050-0045 -

0.040 -0El 0.035

E-01 0.030 l

E-02 0.025 lE-03 x E-04 0.015 XE E

E-08 00

E-20 0.005 0000 0-0 0

0 0 10-06-03 01-14-04 04-23-04 08-01-04 11-09-04 02-17-05 Measured airborne I-131 concentrations continue exhibit small positive and negative values clustered around zero (Figure 11-2) with only 70 of the 310 individual analyses (23%) being statistically greater than zero. Although the Figure 11-2 2004 Airborne I-131 Concentration Frequency 2004 Airborne 1-131 60 C 40 -

20 0

-22

-16

-10

-4 1

7 13 19 Air 1-131 (pCi/m3 x 1000)

In Figure 11-2 x-axis number represents the upper bound of a range. For example, "1" indicates the range -I to +1, -10 indicates the range -12 to -10, etc.

38

distribution is not as symmetrically distributed around zero as in previous years, this I-131 distribution is attributed to the statistical variation expected when making measurements of a sample with no I-131. Supporting this conclusion is that the 70 positive, non-zero values are distributed fairly uniformly throughout the year whereas PBNP emitted airborne I-131 only in May of 2004 when only six positive I-131 values were obtained. One of the six occurrences was at the background sampling site where no I-131 should be found. Therefore, it is concluded that the May release of airborne I-131 had no measurable impact on the environment Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Neither the indicator nor control locations show results, which on average are significantly different than zero. Be-7, a naturally occurring radionuclide, was measured in quarterly composites of all samples with an average of 0.060 pCi/mi3. This is comparable to the average of 0.059 pCi/m3 at the control site. Naturally occurring radionuclides are not required to be measured by the PBNP REMP, however, quantification of such nuclides serve as a means to monitor the internal consistency of the vendor's analytical program.

In summary, the air data for 2004 demonstrate the operation of PBNP did not have an impact on the surrounding environment.

11.4 Lake Water For the suite of REMP-specified gamma emitting radionuclides, reported concentrations continue to occur as small negative and positive values scattered around zero, indicating no radiological impact from the operation of PBNP.

Aliquots of the monthly samples are composted quarterly and analyzed for Sr-89/90 and for tritium. Sr-90 still persists in Lake Michigan from radioactive fallout. Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a naturally occurring radionuclide. The lake water samples collected and analyzed in 2004 for H-3 range from ND (non-detectable) to 1186 pCifL (4th quarter) at a site north of PBNP. Because typical H-3 values are in the range of 100-300 pCi/l, the individual months of Oct. -Dec. were analyzed for tritium and the following results obtained: Oct., 208 + 68; Nov., 3208 +/- 179; and Dec., 145 +/- 95. The 3208 pCifl value is 0.32% of the effluent limit of 10 CFR 20, Appendix B, Table 2. Based on PBNP liquid discharge records, we conclude that the November 2004 tritium concentration result from sampling soon after a liquid discharge. These results indicate a minimal impact upon the waters of Lake Michigan.

39

11.5 Algae Filamentous algae attached to rocks along the Lake Michigan shoreline are known to concentrate radionuclides from the water with concentration factor over a thousand for certain radionuclides. Small, positive concentrations of Cs-137, and Co-58/60 were found. Typically, the only fission product observed is Cs-137 with averages over years 1995-2003 of 0.034, 0.050, 0.030, 0.027, 0.031, 0.027, 0.019, 0.019, and 0.010; all of which are less than the LLD (0.25 pCi/g). Likewise, no observations above the LLD were made in 2004, although small positive values for Cs-137 as well as Co-58/60 occurred. The occurrence of Cs-137 in the environment can also be attributed to the fallout of events from the past such as weapons testing and events like Chernobyl. Massive resuspension events due to wind stress redistribute Cs-137 throughout Lake Michigan and make the Cs-137 more available to the algae. These events are visible on satellite photographs of the Lake. In 1976 after a Chinese weapons test, Cs-137 concentrations in algae reached 1.2 pCi/g. The concentrations of the naturally occurring radionuclides Be-7 and K-40 in the algae continue to be 10 and 100 times higher, respectively, than Cs-137 and Co-58/60. Because PBNP released small amount of these latter radionuclides during the year, these results may be the result of plant activities.

However, because the results are below the LLD, the results also could represent the expected distribution of analytical results around zero expected from the statistical nature of radioactive decay when the specific radionuclide is either not present or present in amount well below the LLD. If the cesium and cobalt concentrations result from PBNP effluents, then the algae data indicate only a minor effect in the vicinity of PBNP during 2004.

11.6 Fish No specified fission/corrosion radionuclide concentrations in fish greater than the required LLD were found in 2004. Low levels of Mn-54, Fe-59, and Co-58 were found in 3 of 10 fish sampled during the year. Although PBNP released these radionuclides during the year, Zn-65 and Co-60 which PBNP also released were not found, it is unlikely that the Mn-54, Fe-59, and Co-58 few positive results represent analytical fluctuations due to the statistical nature of radioactivity.

Statistically positive Cs-137 concentrations were found in 9 of the 10 fish. The highest Cs-137 value of 0.074 pCi/g is considerably less than the high of 2.8 pCi/g as seen in PBNP samples obtained in the mid-1970s during the Chinese weapons tests. The Cs-137 results are consistent with accumulation due to the recycling of atmospheric weapons testing fallout Cs-137 in Lake Michigan. The concentration of naturally occurring K-40 is about 50-100 times higher than the highest Cs-137 concentration. There is no indication of a plant effect.

40

11.7 Well Water All of the isotopic well water results are less than the required LLD. Except for one tritium value, no specific radionuclides were detected. The one positive H-3 value is determined to be a false positive because of the impermeable geological stratum which separates the surface ground water from the aquifer from which the well water is obtained. The results indicate that PBNP effluents are not getting into the aquifer supplying drinking water to PBNP.

11.8 Soil Cs-137 from weapons testing and the Chernobyl accident fallout continue to be present in soil samples at about 1% of the levels of naturally occurring K40. As seen in the following table the average gross beta result is not significantly different from those values observed in the past. There is no indication of a plant effect.

Table 11-5 Average Gross Beta Concentrations in Soil Year Activity (pCi/g) 1993 23.6 1994 19.4 1995 18.0 1996 19.4 1997 22.8 1998 20.0 1999 23.1 2000 22.1 2001 23.5 2002 21.9 2003 22.5 2004 24.3 11.9 Shoreline Sediment Shoreline sediment consists of beach sand and other sediments washed up on the Lake Michigan shore. As in soil samples, the only non-naturally occurring radionuclide found in these samples is Cs-137 and its concentration (pCi/g) is at 1% or less of the naturally occurring concentrations of K-40. The Cs-137 41

concentrations of the shoreline sediment are about one-tenth of that found in soils.

The shoreline sediment data indicate no radiological effects of the plant operation.

11.10 Vegetation Although the naturally occurring radionuclides Be-7 and K40 are found in all of the vegetation samples, the programmatically specified radionuclides are all below the required LD. The Be-7 and K40 concentrations are about 100 times higher than the Cs-137 concentrations which are found only in 3 of the 24 samples.

None of the annual average concentrations are different from zero. The 2004 sampling results give no indication of a plant effect.

11.11 Land Use Census In accordance with the requirements of Section 2.5 of the Environmental Manual, a visual verification of animals grazing in the vicinity of the Point Beach Nuclear Plant site boundary was completed on August 11, 2004, to ensure that the milk sampling locations remain as conservative as practicable. No significant change in the use of pasturelands was noted. Therefore, the existing milk-sampling program continues to be acceptable.

12.0 REMP CONCLUSION Based on the analytical results from the 805 environmental samples and from 116 sets of TLDs that comprised the PBNP REMP for 2004, PBNP effluents had no discemable, permanent effect on the surrounding environs. These results demonstrate that PBNP continues to have good controls on fuel integrity and on the waste processing. The control of effluents from PBNP continues to be acceptable pursuant to the ALARA criteria of 10 CFR 50.34a.

42

APPENDIX A Environmental, Inc. Midwest Laboratory Final Report for the Pont Beach Nuclear Plant Reporting Period: January - December 2004

. v-9 I.--.

-x....

-7 Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

Northbrork, IL. 60062-2310 (847) 564-0700 fax (847) 564-4517 FINAL REPORT TO WISCONSIN ELECTRIC POWER COMPANY MILWAUKEE, WISCONSIN RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

FOR THE POINT BEACH NUCLEAR PLANT TWO RIVERS, WISCONSIN PREPARED AND SUBMITTED BY ENVIRONMENTAL, INC., MIDWEST LABORATORY Project Number: 8006 Reporting Period: January-December, 2004 Reviewed and Approved by -

Date 02 200SX K

B. Grob a oratory Manager Distribution: K. Johansen

Section POINT BEACH NUCLEAR PLANT TABLE OF CONTENTS Page List of Tables.......................

iii INTRODUCTION.......................

1 LISTING OF MISSED SAMPLES........................

2 1.0 2.0 ApDendices A

B C

Interlaboratory Comparison Program Results........................... A-1 Data Reporting Conventions........

......................... B-1 Sampling Program and Locations.............

.................... C-1 ii

POINT BEACH NUCLEAR PLANT LIST OF TABLES Title Page Airborne Particulates and Iodine-131 Location E-01, Meteorological Tower..........

..................... 4 Location E-02, Site Boundary Control Center................................5 Location E-03, West Boundary.....................

6 Location E-04, North Boundary.....................

7 Location E-08, G. J. Francar Residence...................................

8 Location E-20, Silver Lake College...........

........................9 Airborne Particulates, Gamma Isotopic Analyses.....................

............. 10 Milk..................................

11 Well Water..................................

17 Lake Water..................................

18 Lake Water, Analyses on Quarterly Composites.................

................. 22 Fish..................................

25 Shoreline Sediments..................................

28 Soil...........

30 Vegetation...........

32 Aquatic Vegetation...........

35 Gamma Radiation, as Measured by TLDs............................

36 iii

POINT BEACH NUCLEAR PLANT

1.0 INTRODUCTION

The following constitutes the current Monthly Progress Report for the Environmental Radiological Monitoring Program conducted at the Point Beach Nuclear Plant, Two Rivers, Wisconsin. Results of completed analyses are presented in the attached tables. Missing entries indicate analyses that are not completed. These results will appear in subsequent reports. Data tables reflect sample analysis results for both Technical Specification requirements and Special Interest locations and samples are randomly selected within the Program monitoring area to provide additional data for cross-comparisons.

Data obtained in the program are well within the ranges previously encountered in the program and to be expected in the environmental media sampled. None of the media sampled during the current month contained radioactivity attributable to the operation of Point Beach Nuclear Plant.

For all gamma isotopic analyses, the spectrum is computer scanned from 80 to 2048 KeV. Specifically included are Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106,1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144.

Naturally occurring gamma-emitters, such as K-40 and Ra daughters, are frequently detected in soil and sediment samples. Specific isotopes listed are K-40, T1-208, Pb-212, Bi-214, Ra-226 and Ac-228. Unless noted otherwise, the results reported under "Other Gammas" are for Co-60 and may be higher or lower for other radionuclides.

All concentrations, except gross beta, are decay corrected to the time of collection.

Dashes in the NRequired LLD" column signify that LLD for specific isotope is not required by Point Beach Nuclear Power Plant.

All samples were collected within the scheduled period unless noted otherwise in the Listina of Missed Samoles.

1

POTNT BEACH NUCT FAR PLANT

1.0 INTRODUCTION

The following constitutes the final 2004 Monthly Progress Report for the Environmental Radiological Monitoring Program conducted at the Point Beach Nuclear Plant, Two Rivers, Wisconsin. Results of analyses are presented in the attached tables. Data tables reflect sample analysis results for both Technical Specification requirements and Special Interest locations and samples are randomly selected within the Program monitoring area to provide additional data for cross-comparisons.

For gamma isotopic analyses, the spectrum covers an energy range from 80 to 2048 KeV. Specifically included are Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. Naturally occurring gamma-emitters, such as K-40 and Ra daughters, are frequently detected in soil and sediment samples. Specific isotopes listed are K-40, TI-208, Pb-212, Bi-214, Ra-226 and Ac-228. Unless noted otherwise, the results reported under 'Other Gammas" are for Co-60 and may be higher or lower for other radionuclides.

All concentrations, except gross beta, are decay corrected to the time of collection.

All samples were collected within the scheduled period unless noted otherwise in the Listing of Missed Samples.

I

POINT BEACH NUCLEAR PLANT 2.0 LISTING OF MISSED SAMPLES Expected Collection Sample Type Location Date Reason LW AP/AI AP/AI E-01, 05, 06, E-33 E-02 E-04 February '04 3/10/2004 7/28/2004 Samples not sent.

Sampler not running.

Power failure at sampler.

NOTE: Page 3 is intentionally left out.

2

POINT BEACH NUCLEAR PLANT Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-01, Meteorological Tower Units: pCVM3 Collection: Continuous, weekly exchange.

Date Vol.

Collected (M3)

Gross Beta 1-131 Date Vol.

Collected (m3)

Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-07-04 01 -1 5-04 01 04 01-28-04 369 0.033 +/- 0.003 355 0.035 + 0.003 263 0.015 +/- 0.003 298 0.021 +/- 0.004 02-04-04 307 0.045 +/- 0.004 02-11-04 319 0.031 +/- 0.004 02-19-04 372 0.024 +/- 0.003 02-26-04 277 0.033 :+/- 0.004 03-03-04 325 0.021 +/- 0.003

-0.001 +/- 0.004

-0.002 +/- 0.005

-0.002 +/- 0.005 0.001 +/- 0.005 0.007 +/- 0.006 0.001 +/- 0.005

-0.010 +/-0.004

-0.001 :t 0.007 0.007 +/- 0.005 0.010 +/- 0.006 0.006 +/- 0.005 0.010 +/- 0.004 0.003 +/- 0.005 07-07-04 07-14-04 07-21-04 07-28-04 08-03-04 08-11-04 08-18-04 08-26-04 09-02-04 09-08-04 09-16-04 09-23-04 09-30-04 330 0.009 +/- 0.002 326 0.012 +/-0.003 315 0.020 +/-0.003 322 0.018 +/-0.003 264 0.028 +/- 0.004 343 0.021 +/- 0.003 298 0.017 +/- 0.003 342 0.018 +/- 0.003 300 0.011 +/-0.003 255 0.032 +/- 0.004 300 0.024 +/- 0.003 342 0.026 +/- 0.004 301 0.021 +/-0.003

-0.004 +/- 0.004

-0.006 +/- 0.005 0.008 +/- 0.005

-0.002 +/- 0.005

-0.007 +/- 0.006 0.005 +/- 0.005

-0.002 +/- 0.006 0.004 +/- 0.005 0.007 +/- 0.006

-0.002 +/- 0.007 0.006 +/- 0.005 0.006 +/- 0.005

-0.005 +/- 0.006 03-10-04 03-18-04 03-26-04 04-03-04 321 0.033 +/- 0.003 369 0.017 +/- 0.003 370 0.017 +/- 0.003 371 0.013 +/- 0.003 1st Quarter 3rd Quarter Mean+/- s.d.

0.026 +/- 0.010 04-11-04 378 0.018 +/- 0.003 04-17-04 276 0.013 + 0.004 04-24-04 315 0.016 +/- 0.003 05-01-04 329 0.017 +/-0.003 05-08-04 326 0.013 +/- 0.003 05-15-04 322 0.016 +/- 0.003 05-23-04 372 0.015 +/- 0.003 05-29-04 267 0.010 +/- 0.003 06-05-04 333 0.012 +/- 0.002 06-11-04 282 0.017 +/- 0.004 06-17-04 270 0.014 +/-0.003 06-23-04 278 0.013 +/-0.003 06-30-04 320 0.011 +/-0.003 0.002 +/- 0.006 0.006 +/- 0.004 0.001 +/- 0.006

-0.006 +/- 0.005 0.001 +/-0.005 0.004 +/- 0.005 0.008 +/- 0.005

-0.002 +/-0.004 0.001 +/- 0.006

-0.009 +/-0.004 0.011 +/-0.007 0.008 +/- 0.006

-0.005 +/- 0.006

-0.007 +/- 0.005 Mean+/- s.d.

0.020 +/- 0.007 10-06-04 260 0.019 +/- 0.003 10-14-04 341 0.018 +/- 0.003 10-21-04 296 0.014 +/-0.003 10-27-04 259 0.015 +/-0.004 11-05-04 385 0.014 +/-0.002 11-10-04 212 0.027 +/-0.005 11-17-04 298 0.025 +/- 0.004 11-24-04 299 0.025 +/-0.003 12-01-04 299 0.022 +/- 0.003 12-09-04 341 0.025 +/- 0.003 12-16-04 302 0.026 +/-0.003 12-22-04 257 0.022 +/- 0.004 12-29-04 296 0.030 +/-0.003 0.001 +/- 0.005 0.012 +/- 0.006 0.001 +/-0.005 0.002 +/- 0.006

-0.009 +/- 0.007 0.001 +/-0.004

-0.002 +/- 0.008 0.002 +/- 0.005 0.014 +/- 0.005

-0.011 +/-0.005

-0.003 +/- 0.005 0.014 +/- 0.006

-0.012 +/- 0.007 0.013 +/- 0.005 2nd Quarter Mean+/- s.d.

4th Quarter Mean+/- s.d.

0.014 +/- 0.002 0.001 +/- 0.006 0.022 +/- 0.005 0.002 +/- 0.009 Cumulative Averaqe 0.020 +/- 0.008 0.001 +/- 0.007 4

POINT BEACH NUCLEAR PLANT 5

POINT BEACH NUCLEAR PLANT Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-02, Site Boundary Control Center Units: pCVm3 Collection: Continuous, weekly exchange.

Date Vol.

Collected (m3)

Gross Beta 1-131 Date Vol.

Collected (M 3 )

Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-07-04 01-15-04 01-21-04 01-28-04 02-05-04 02-11-04 02-19-04 02-26-04 03-03-04 345 0.036 +/- 0.003 0.005 +/- 0.005 343 0.034 +/- 0.003 0.005 +/- 0.005 263 0.017 +/- 0.003 0.005 +/- 0.006 299 0.022 +/- 0.004 -0.004 +/- 0.006 345 0.044 +/- 0.004 0.002 +/- 0.005 259 0.038 +/- 0.005 0.006 +/- 0.007 346 0.023 +/- 0.003 -0.004 +/- 0.005 260 0.028 +/- 0.004 0.001 +/- 0.006 305 0.022 +/- 0.003 0.006 +/- 0.005 07-07-04 07-14-04 07-21-04 07-28-04 08-03-04 08-11-04 08-18-04 08-26-04 09-02-04 309 0.010 +/- 0.002 296 0.010 +/- 0.003 303 0.021 +/- 0.004 293 0.019 +/- 0.003 241 0.029 +/- 0.004 325 0.020 +/- 0.003 283 0.017 +/- 0.003 335 0.020 +/- 0.003 293 0.012 +/- 0.003 0.002 +/- 0.006 0.007 +/- 0.005 0.002 +/- 0.005 0.005 +/- 0.005 0.007 +/- 0.006 0.011 +/- 0.005 0.007 +/- 0.006 0.002 +/- 0.005

-0.010 +/- 0.005 03-10-04 ND" 03-18-04 345 0.020 +/- 0.003 03-26-04 346 0.019 +/- 0.003 04-03-04 346 0.017 +/- 0.003

-0.008 +/- 0.004

-0.013 +/- 0.005 0.003 +/- 0.005 09-08-04 09-16-04 09-23-04 09-30-04 251 0.035 +/- 0.004 294 0.024 +/- 0.003 336 0.026 +/- 0.004 294 0.021 +/- 0.003 0.011 +/- 0.006 0.005 +/- 0.006 0.001 +/- 0.005 0.005 +/- 0.006 1st Quarter Mean+/- s.d.

0.027 +/- 0.009 0.000 +/- 0.006 3rd Quarter Mean+/- s.d.

0.020 +/- 0.007 0.004 +/- 0.005 04-11-04 04-17-04 04-24-04 05-01-04 05-08-04 05-15-04 05-23-04 05-29-04 06-05-04 06-11-04 06-17-04 06-23-04 06-30-04 354 0.015 +/-0.003 258 0.013 +/- 0.004 294 0.016 +/- 0.003 307 0.018 +/- 0.003 305 0.017 +/- 0.003 301 0.015 +/-0.003 347 0.014 0.003 250 0.009 +/- 0.003 311 0.015 +/- 0.003 263 0.019 +/- 0.004 253 0.016 +/-0.003 260 0.014 +/- 0.003 300 0.011 +/-0.003

-0.005 +/- 0.004 0.007 +/- 0.006 0.008 +/- 0.005 0.010 +/- 0.005 0.003 +/- 0.005

-0.001 +/- 0.005 0.008 +/- 0.005 0.006 +/- 0.007 0.006 +/- 0.005 0.009 +/- 0.006 0.001 +/- 0.007 0.011 +/- 0.006

-0.004 +/- 0.006 10-06-04 10-14-04 10-21-04 10-27-04 11-05-04 11-10-04 11-17-04 11-24-04 12-01 -04 12-09-04 12-16-04 12-22-04 12-29-04 256 0.020 +/- 0.004 333 0.022 +/- 0.003 291 0.011 +/-0.003 254 0.015 +/-0.004 374 0.015 +/- 0.002 214 0.021 +/-0.005 289 0.026 +/- 0.004 294 0.032 +/- 0.004 302 0.021 +/- 0.003 346 0.021 +/- 0.003 306 0.029 +/- 0.003 268 0.024 +/- 0.004 301 0.031 +/- 0.003 0.008 +/- 0.006

-0.003 +/- 0.005 0.005 +/- 0.005 0.008 +/- 0.007

-0.018 +/- 0.004

-0.005 +/- 0.007

-0.007 +/- 0.006

-0.005 +/- 0.006

-0.015 +/- 0.006

-0.001 +/- 0.005 0.004 +/- 0.005

-0.020 +/- 0.008 0.005 +/- 0.006 2nd Quarter Mean+/- s.d.

4th Quarter 0.005 +/- 0.005 Mean+/- s.d.

0.015 +/- 0.003 0.022 +/- 0.006

-0.003 +/- 0.009 Cumulative Averace 0.021 +/- 0.008 0.001 +/- 0.007 a"ND" = No data; see Table 2.0, Listing of Missed Samples.

5

POINT BEACH NUCLEAR PLANT Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-03, West Boundary Units: pCLim 3 Collection: Continuous, weekly exchange.

Date Vol.

Collected (m3)

Gross Beta Required LLD 0.010 Date Vol.

Collected (m3)

Gross Beta 1-131 1-131 0.030 01-07-04 01 04 01-21-04 01-28-04 346 0.033 +/- 0.003 0.001 +/- 0.005 343 0.027 +/- 0.003 -0.001 +/- 0.005 261 0.018 +/- 0.003 0.006 +/- 0.006 308 0.018 +/- 0.003 0.006 +/- 0.004 Required L 07-07-04 07-14-04 07-21-04 07-28-04 08-03-04

.LD 0.010 308 0.009 +/- 0.002 304 0.014 +/- 0.003 295 0.022 +/- 0.004 352 0.018 +/- 0.003 258 0.028 +/- 0.004 0.030 0.001 +/- 0.005 0.016 +/- 0.005

-0.006 +/- 0.006

-0.012 +/- 0.005 0.003 +/- 0.006 02-05-04 02-11-04 02-19-04 02-26-04 03-03-04 338 0.040 +/- 0.004 0.007 +/- 0.004 259 0.036 +/- 0.004 -0.015 +/- 0.007 347 0.024 +/- 0.003 0.006 +/- 0.005 260 0.032 +/- 0.004 -0.004 +/- 0.006 304 0.018 +/- 0.003 0.004 +/- 0.005 08-11-04 08-18-04 08-26-04 09-02-04 09-08-04 09-16-04 09-23-04 09-30-04 347 0.017 +/- 0.003 302 0.019 +/- 0.003 345 0.017 +/- 0.003 302 0.013 +/- 0.003 258 0.033 +/- 0.004 304 0.023 +/- 0.003 345 0.026 +/- 0.004 304 0.016 +/- 0.003 0.001 +/- 0.004

-0.002 +/- 0.006

-0.001 +/- 0.005 0.001 +/- 0.006 0.003 +/- 0.007 0.005 +/- 0.005

-0.006 +/- 0.005 0.002 +/- 0.005 03-10-04 300 0.033 +/- 0.003 -0.001 +/- 0.005 03-18-04 345 0.017 +/- 0.003 -0.012 +/- 0.005 03-26-04 345 0.019 +/- 0.003 0.006 +/- 0.005 04-03-04 346 0.015 +/- 0.003 -0.003 +/- 0.005 1st Quarter Mean+/- s.d.

0.025 +/- 0.009 0.000 +/- 0.007 3rd Quarter Mean+/- s.d.

0.020 +/- 0.007 0.000 +/- 0.007 04-11-04 04-17-04 04-24-04 05-01-04 354 0.017 +/- 0.003 -0.005 +/- 0.004 258 0.013 +/- 0.004 0.011 +/- 0.007 293 0.016 +/- 0.003 -0.003 +/- 0.006 308 0.017 +/- 0.003 0.003 +/- 0.006 10-06-04

'10-14-04 10-21 -04 10-27-04 263 0.016 +/- 0.003 346 0.018 +/- 0.003 297 0.011 +/- 0.002 262 0.012 +/- 0.003

-0.006 +/- 0.007

-0.001 +/- 0.004

-0.006 +/- 0.006 0.002 +/- 0.007 05-08-04 05-15-04 05-23-04 05-29-04 06-05-04 06-11-04 06-17-04 06-23-04 06-30-04 304 0.018 +/- 0.003 0.002 +/- 0.006 301 0.015 +/- 0.003 -0.001 +/- 0.006 347 0.013 +/- 0.003 -0.003 +/-0.004 250 0.012 +/- 0.004 0.003 +/- 0.006 311 0.017 +/- 0.003 -0.005 +/- 0.005 263 0.020 +/- 0.004 0.005 +/- 0.006 253 0.0i4 +/- 0.003 0.009 +/- 0.006 260 0.015 +/- 0.003 -0.007 +/- 0.007 300 0.012 +/- 0.003 0.005 +/- 0.006 11-05-04 11-10-04 11-17-04 11-24-04 12-01 -04 12-09-04 12-16-04 12-22-04 12-29-04 386 0.012 +/- 0.002 220 0.020 +/- 0.004 298 0.021 +/- 0.004 303 0.028 +/- 0.003 303 0.021 +/- 0.003 344 0.022 +/- 0.003 306 0.024 +/- 0.003 260 0.024 +/- 0.004 300 0.031 +/- 0.004

-0.011 +/- 0.004

-0.021 +/- 0.008 0.008 +/- 0.005

-0.009 +/- 0.005 0.001 +/- 0.006 0.001 +/- 0.005

-0.004 +/- 0.006 0.015 +/- 0.006

-0.003 +/- 0.006 2nd Quarter Mean+/- s.d.

0.015 +/- 0.002 0.001 +/- 0.006 4th Quarter Mean+/- s.d.

0.020 +/- 0.006

-0.003 +/- 0.008 Cumulative Averaae 0.020 +/- 0.007 0.000 +/- 0.007 6

POINT BEACH NUCLEAR PLANT Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-04, North Boundary Units: pCVm3 Collection: Continuous, weekly exchange.

Date Vol.

Collected (m3)

Gross Beta 1-131 Date Vol.

Collected (m3)

Gross Beta 1-131 Reauired LLD 0.010 0.030 Reauired LLD 0.010 0.030 01-07-04 346 0.034 +/- 0.003 01-15-04 344 0.032 +/-0.003 01-21-04 260 0.016 +/-0.003 01-28-04 308 0.018 +/-0.003 02-05-04 339 0.043 +/- 0.004 02-11-04 259 0.032 +/-0.004 02-19-4 346 0.027 +/- 0.003 02-26-04 261 0.033 +/-0.004 03-03-04 303 0.019 +/- 0.003 03-10-04 300 0.031 +/- 0.003 03-18-04 347 0.020 +/- 0.003 03-26-04 343 0.021 +/- 0.003 04-03-04 346 0.015 +/-0.003 1st Quarter

-0.001 +/- 0.005 0.000 +/- 0.005 0.011 +/-t0.005

-0.005 +/-0.005 0.004 +/- 0.005 0.006 +/-t 0.007 0.010 +/- 0.004 0.001 +/- 0.006 0.005 +/- 0.006 0.002 +/- 0.006

-0.010 +/-0.005 0.005 +/- 0.005

-0.008 :+/-0.005 07-07-04 07-14-04 07-21-04 07-28-04 308 0.008 +/- 0.002 0.001 +/- 0.005 295 0.010 +/- 0.003

-0.008 +/- 0.006 306 0.020 +/- 0.003 0.007 +/- 0.005 NDa 08-03-04 236 0.032 :+/-0.004 0.017 +/- 0.007 08-11-04 08-18-04 08-26-04 09-02-04 09-08-04 09-16-04 09-23-04 09-30-04 319 0.020 +/- 0.003 286 0.022 +/- 0.004 328 0.018 +/-0.003 287 0.011 +/- 0.003 245 0.032 +/- 0.004 289 0.026 +/- 0.003 327 0.032 +/- 0.004 289 0.027 +/- 0.004 0.007 +/-0.006 0.002 +/-0.007 0.003 +/-0.006 0.000 +/- 0.006 0.010 :0.006

-0.003 +/- 0.005 0.006 +/- 0.005 0.005 +/-0.006 3rd Quarter Mean+/- s.d.

04-11-04 04-17-04 04-24-04 05-01-04 05-08-04 05-15-04 05-23-04 05-29-04 06-05-04 06-11-04 06-17-04 06-23-04 06-30-04 0.026 +/- 0.009 354 0.017 +/- 0.003 258 0.012 +/- 0.004 294 0.0i9 +/- 0.003 308 0.016 0.003 304 0.018 +/- 0.003 301 0.016 +/--0.003 347 0.011 +/-0.003 250 0.007 +/- 0.003 311 0.013 +/- 0.003 263 0.018 +/- 0.004 253 0.016 :0.003 260 0.012 +/- 0.003 300 0.011

+/- 0.003 0.002 +/- 0.006 0.007 +/- 0.004 0.003 +/-0.006

-0.009 +/-0.005 0.006 +/- 0.006 0.001

+/- 0.006 0.002 +/- 0.005

-0.002 +/- 0.004

-0.012 :+/-0.006

-0.008 +/- 0.006

-0.009 +/- 0.006 0.009 +/- 0.006

-0.008 +/- 0.005

-0.005 +/- 0.005 Mean+/- s.d.

10-06-04 10-14-04 10-21-04 10-27-04 1 14-054 11-10-04 11-17-04 11-24-04 12-01-04 12-09-04 12-16-04 12-22-04 12-29-04 0.022 +/- 0.009 250 0.018 +/- 0.003 328 0.019 +/-t0.003 284 0.010 +/- 0.003 249 0.018 +/-0.004 366 0.019 +/- 0.003 210 0.024 +/- 0.005 302 0.025 +/- 0.004 307 0.031 +/- 0.004 306 0.022 +/- 0.003 339 0.023 +/- 0.003 290 0.030 :+/- 0.004 248 0.026 +/- 0.004 284 0.037 +/- 0.004 0.004 +/- 0.006

-0.002 +/-0.007

-0.002 :+/-0.006

-0.006 +/- 0.006 0.018 :0.007

-0.001 +/- 0.004

-0.009 +/- 0.008 0.006 +/- 0.005

-0.011 +/- 0.006

-0.005 :+/- 0.005

-0.007 +/- 0.005

-0.008 : 0.006

-0.002 +/- 0.006 0.001 +/- 0.006 2nd Quarter 4th Quarter Meant s.d.

=

Mean+/-s.d.

0.014 +/-0.004

-0.002 +/- 0.007 0.023 +/- 0.007

-0.002 +/- 0.007 Cumulative Average 0.021 +/-0.008 0.000 +/- 0.007 a "ND' = No data; see Table 2.0, Listing of Missed Samples.

7

POINT BEACH NUCLEAR PLANT Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-08, G.J. Francar Residence Units: pCi/m3 Collection: Continuous, weekly exchange.

Date Vol.

Collected (m 3)

Gross Beta 1-131 Date Vol.

Collected (m 3)

Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-07-04 01-15-04 01-21-04 01-28-04 02-05-04 02-11-04 02-19-04 02-26-04 03-03-04 03-10-04 03-18-04 03-26-04 04-03-04 344 0.031 +/-0.003 356 0.026 0.003 266 0.018 +/-0.003 309 0.021 +/-0.004 340 0.043 +/- 0.004 260 0.030 +/- 0.004 346 0.029 +/- 0.003 260 0.030 +/- 0.004 304 0.019 t 0.003 300 0.029 +/- 0.003 347 0.016 +/- 0.003 343 0.020 +/- 0.003 346 0.016 +/- 0.003 0.008 +/- 0.005 0.000 +/- 0.004 0.001 +/- 0.006

-0.004 +/- 0.005

-0.003 +/- 0.005 0.001 +/- 0.007

-0.002 +/- 0.005 0.016 +/- 0.006

-0.004 +/- 0.005 0.006 +/- 0.006 0.004 +/- 0.005 0.003 +/- 0.005 0.001 +/- 0.004 07-07-04 07-14-04 07-21-04 07-28-04 08-03-04 08-11-04 08-18-04 08-26-04 09-02-04 09-08-04 09-16-04 09-23-04 09-30-04 308 296 304 281 239 322 280 322 286 244 295 328 283 0.011 +/- 0.003 0.003 +/- 0.006 0.014

0.003 0.006 +/- 0.006 0.020 +/- 0.003 0.000 +/- 0.005 0.017 +/- 0.003 0.001 t 0.007 0.029 +/- 0.004 0.001 +/- 0.008 0.015 +/- 0.003 -0.005 +/- 0.005 0.021 +/- 0.004 0.004 +/- 0.006 0.017 +/- 0.003 0.005 +/- 0.005 0.011 +/- 0.003 -0.002 +/- 0.006 0.033 +/- 0.004 -0.014 +/- 0.006 0.027 +/- 0.003 0.003 +/- 0.006 0.022 +/- 0.003 -0.007 +/- 0.005 0.021 +/- 0.003 -0.011 +/-0.006 1st Quarter Mean+/- s.d.

0.025 +/- 0.008 0.002 +/- 0.006 3rd Quarter Mean+/- s.d.

0.020 +/- 0.007 -0.001 +/- 0.006 04-11-04 04-17-04 04-24-04 05-01-04 05-08-04 05-15-04 05-23-04 05-29-04 06-05-04 06-11-04 06-17-04 06-23-04 06-30-04 354 0.018 +/- 0.003 -0.002 +/- 0.004 258 0.015 +/- 0.004 -0.011 +/- 0.007 293 0.016 +/-0.003 0.008 +/- 0.005 308 0.015 +/- 0.003 -0.004 +/- 0.005 305 0.017 +/- 0.003 0.004 +/- 0.005 301 0.015 +/- 0.003 -0.009 +/- 0.005 348 0.010 +/- 0.003 0.013 +/- 0.005 250 0.011 +/- 0.003 -0.014 +/- 0.007 311 0.014 +/-0.003 0.006 +/- 0.005 264 0.019 0.004 -0.004 +/- 0.006 252 0.012 +/- 0.003 0.003 +/- 0.007 260 0.016 +/-0.003 0.003 +/- 0.007 300 0.010 +/- 0.003 -0.004 +/- 0.006 10-06-04 10-14-04 10-21-04 10-27-04 11-05-04 11-10-04 11-17-04 11-24-04 12-01-04 12-09-04 12-16-04 12-22-04 12-29-04 244 325 274 244 359 205 296 300 302 340 303 259 297 0.020 +/- 0.004 -0.001 +/- 0.007 0.022 +/- 0.003 0.004 +/- 0.006 0.011 +/- 0.003 -0.005 t 0.006 0.014 +/- 0.004 -0.004 +/- 0.008 0.015 +/- 0.002 -0.001 +/- 0.004 0.026 +/- 0.005 0.007 +/- 0.007 0.026 +/- 0.004 -0.014 ::0.006 0.031 +/- 0.004 -0.001 +/- 0.005 0.023 +/- 0.003 -0.006 +/- 0.005 0.024 + 0.003 0.005 +/- 0.005 0.029 +/- 0.003 0.002 +/- 0.006 0.026 +/- 0.004 -0.004 +/- 0.006 0.034 +/- 0.004 0.002 +/- 0.006 2nd Quarter Mean+/- s.d.

0.014 +/- 0.003 -0.001 +/- 0.008 4th Quarter Mean+/- s.d.

0.023 +/- 0.007 -0.001 +/- 0.005 Cumulative Average 0.021 +/- 0.007 0.000 +/- 0.006 8

POINT BEACH NUCLEAR PLANT Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-20, Silver Lake Units: pCVm3 Collection: Continuous, weekly exchange.

Date Vol.

Collected (m 3)

Gross Beta 1-131 Date Vol.

Collected (m 3)

Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-07-04 01 04 01-21-04 01-28-04 02-04-04 02-11-04 02-19-04 02-26-04 03-03-04 03-10-04 03-18-044 03-26-04 04-03-04 348 330 251 301 306 299 348 258 305 299 348 342 346 0.033 +/- 0.003 0.031 +/- 0.003 0.019 +/- 0.003 0.023 +/- 0.004 0.043 +/- 0.004 0.037 +/- 0.004 0.028 +/- 0.003 0.035 +/- 0.005 0.024 +/- 0.003 0.019 0.003 0.019 +/- 0.003 0.018 +/-0.003 0.015 +/-0.003 0.007 +/- 0.005 0.010 +/-0.006 0.002 +/-0.006 0.011 +/-0.005

-0.006 +/- 0.005

-0.003 +/-0.006

-0.003 +/- 0.005 0.017 +/- 0.007

-0.005 +/- 0.005

-0.011 +/- 0.006 0.006 +/- 0.005 0.004 +/- 0.005

-0.008 +/-t 0.005 07-07-04 07-14-04 07-21-04 07-28-04 083-04 08-11-04 08-18-04 08-26-04 09-02-04 09-08-04 09-16-04 09-23-04 09-30-04 306 299 303 304 247 348 301 345 301 260 305 342 304 0.010 +/-0.002 0.013 +/-0.003 0.021 +/- 0.004 0.018 +/- 0.003 0.031 +/- 0.004 0.017 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.003 0.014 +/-0.003 0.034 +/-0.004 0.026 t 0.003 0.025 +/- 0.003 0.020 +/- 0.003 0.006 +/- 0.005 0.013 +/- 0.005 0.013 +/- 0.006

-0.007 +/- 0.005

-0.004 +/- 0.008

-0.004 +/- 0.004 0.006 +/- 0.006 0.012 t0.004 0.011 +/- 0.005

-0.003 +/- 0.006

-0.007 +/- 0.006 0.001 +/- 0.005

-0.002 +/- 0.007 1st Quarter Mean+/- s.d.

3rd Quarter Mean+/- s.d.

0.026 +/- O.009 04-11-04 04-17-04 04-24-04 05-01-04 05-08-04 05-15-04 05-23-04 05-29-04 06-05-04 06-11-04 06-17-04 06-23-04 06-30-04 356 256 297 304 306 300 348 250 312 263 252 262 299 0.019 +/-0.003 0.012 +/- 0.004 0.016 +/- 0.003 0.017 +/-0.003 0.018 +/-0.003 0.018 +/-0.003 0.012 +/-0.003 0.008 +/- 0.003 0.014 +/- 0.003 0.020 +/-0.004 0.013 +/-t0.003 0.040 +/- 0.005 0.011 +/- 0.003 0.002 +/-0.008

-0.008 +/-0.004 0.012 +/-0.006 0.002 +/-0.006

-0.004 +/-0.005

-0.004 +/- 0.006 0.011 +/- 0.005

-0.004 +/- 0.005

-0.017 +/- 0.006

-0.003 +/-0.005

-0.004 +/- 0.005

-0.004 +/- 0.006

-0.002 +/- 0.007 0.006 +/- 0.006 0.021 +/- 0.007 10-06-04 10-14-04 10-21-04 10-27-04 11-05-04 11-10-04 11-17-04 11-24-04 12-01-04 12-09-04 12-16-04 12-22-04 12-294 263 345 302 258 390 216 300 302 301 334 294 262 289 0.020 +/- 0.003 0.023 +/-0.003 0.010 +/- 0.002 0.014 +/-0.004 0.016 +/-0.002 0.025 +/-0.005 0.026 +/- 0.004 0.028 +/-0.003 0.022 +/-0.003 0.022 +/-0.003 0.028 +/-0.004 0.025 +/-0.004 0.031 +/-0.004 0.003 +/-0.008 0.011 +/- 0.006 0.004 +/- 0.004

-0.006 +/-0.006

-0.002 +/-0.007

-0.009 +/- 0.004

-0.002 +/- 0.008

-0.006 +/-0.006 0.009 +/-0.006 0.003 +/-0.005 0.002 +/- 0.006

-0.005 +/- 0.006

-0.001 +/- 0.006 0.003 +/- 0.006 2nd Quarter Mean+/- s.d.

4th Quarter Mean+/- s.d.

0.017 +/- 0.008

-0.001 +/- 0.008 0.022 :t 0.006 0.000 +/- 0.006 Cumulative Average 0.022 +/- 0.008 0.001 +/-0.007 9

POINT BEACH NUCLEAR PL ANT GAMMA EMITTERS IN QUARTERLY COMPOSITES OF AIR PARTICULATE FILTERS (Concentration pCi/m3)

Locatior Lab Code Be-7 Cs-1 34 Cs-1 37 Other Gammas' Volume Reg. LLD (0.05)

(0.06)

(0.10) 1 st Quarter E-01 E-02 E-03 E-04 E-08 E-20 E-01 E-02 E-03 E-04 E-08 E-20 E-01 E-02 E-03 E-04 E-08 E-20 E-01 E-02 E-03 E-04 E-08 E-20 EAP-1707

- 1708

- 1709

- 1710

- 1711

- 1712 EAP-3925

- 3926

- 3927

- 3928

- 3929

- 3930 EAP-6270

- 6271

- 6272

- 6273

- 6274

- 6275 EAP-7840

- 7841

- 7842

- 7843

- 7844

- 7845 0.041 +/- 0.012 0.048 +/- 0.013 0.046 +/- 0.011 0.044 +/- 0.010 0.050 +/- 0.012 0.045 +/- 0.012 0.074 +/- 0.013 0.068 +/- 0.016 0.068 +/-0.015 0.066 t 0.014 0.061 +/- 0.015 0.073 t 0.018 0.074 +/- 0.014 0.082 :+/-0.016 0.055 +/- 0.012 0.072 +/- 0.016 0.071 +/- 0.014 0.061 +/- 0.014 0.063 +/- 0.014 0.048 +/- 0.011 0.052 +/- 0.014 0.059 +/- 0.017 0.061 +/- 0.012 0.056 +/- 0.015

-0.0004 +/- 0.0005

-0.0001 +/- 0.0005 0.0002 +/- 0.0004

-0.0001 +/-0.0006 0.0005 +/- 0.0006 0.0004 +/- 0.0006 0.0001 + 0.0006 0.0003 +/- 0.0005

-0.0002 +/- 0.0005

-0.0001 +/- 0.0008 0.0004 +/- 0.0006 0.0007 +/- 0.0005 0.0003 + 0.0005 0.0004 + 0.0007 0.0004 +/- 0.0006 0.0007 +/- 0.0006 0.0009 +/- 0.0006 0.0004 +/- 0.0006 0.0001 +/-0.0006 0.0005 +/- 0.0006 0.0005 +/- 0.0006 0.0005 +/- 0.0007

-0.0005 +/- 0.0007 0.0004 + 0.0005 0.0001 +/- 0.0004 0.0005 +/- 0.0005

-0.0005 +/- 0.0006

-0.0003 +/- 0.0005

-0.0001 +/- 0.0005

-0.0001 +/- 0.0006

-0.0001 +/- 0.0006 0.0005 +/- 0.0006 0.0001 +/- 0.0005

-0.0001 +/- 0.0006

-0.0002 +/- 0.0006 0.0007 +/- 0.0004 0.0003 +/- 0.0005 0.0007 +/- 0.0006 0.0006 +/- 0.0006 0.0002 +/- 0.0006 0.0003 +/- 0.0005

-0.0004 +/- 0.0007 0.0005 +/- 0.0005 0.0002 +/- 0.0005 0.0004 +/- 0.0006 0.0005 +/- 0.0005

-0.0001 +/- 0.0006

-0.0002 +/- 0.0006 0.0002 +/- 0.0006

-0.0001 +/-0.0006

-0.0001 +/-0.0006 0.0006 +/- 0.0005

-0.0006 +/- 0.0007 0.0003 +/- 0.0005 0.0004 +/- 0.0005 0.0009 +/- 0.0006

-0.0001 +/- 0.0009 0.0001 +/- 0.0006 0.0014 +/- 0.0009 0.0002 +/- 0.0006

-0.0008 +/- 0.0006 0.0001 +/- 0.0007 0.0007 +/- 0.0005

-0.0009 +/- 0.0007

-0.0003 +/- 0.0006

-0.0005 +/- 0.0006 0.0001 +/-0.0006

-0.0001 +/-0.0005 0.0003 +/- 0.0006

-0.0001 +/-0.0007

-0.0001 +/-0.0005 4316 3802 4102 4102 4121 4081 4068 3803 3802 3803 3804 3805 4038 3853 4024 3515 3788 3965 3845 3828 3888 3763 3748 3856 a See Introduction 10

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES (Monthly Collections)

Sample Description and Concentration (pCVL)

Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-1 34 Cs-1 37 Ba-La-140 Other Gammasa Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-1 34 Cs-1 37 Ba-La-1 40 Other Gammasa E-11 Funk Dairy Farm 01-07-04 02-04-04 EMI-77 EMI-459 0.2 +/- 0.8

-0.5 +/- 0.7 1.1 +/- 0.3 1.2 +/- 0.4 0.07 +/-0.13

-0.03 +/- 0.16 1412 +/-t 11i8 1292 +/- 107 1.4 +/- 2.7

-1.1 + 2.3 1.4 +/- 2.5 1.6 +/- 2.4

-0.4 +/- 1.7 0.0 +/- 1.8

-0.1 +/- 2.8 0.7 +/- 2.3 04-07-04 05-05-04 EMI-1502 EMI-2210 0.6 +/-t 0.6

-0.9 +/- 0.9 0.9 +/- 0.3 0.8 +/- 0.4 0.02 +/- 0.16

-0.10 +/- 0.17 1341 +/-119 1411 +/-116 0.8 +/- 2.3 1.2 +/- 2.8

-0.1 +/- 2.5 0.8 +/- 2.7 0.5 +/- 2.1

-0.6 + 2.3

-0.2 +/- 2.4 0.8 + 2.7 03-03-04 EMI-938

-0.1 + 0.5 0.9 +/- 0.3 0.04 +/- 0.19 1315 +/- 126

-1.3 +/-2.9

-0.3 +/- 2.8 0.7 +/- 2.3

-1.4 +/- 2.9 06-02-04 EMI-2710.

-0.9 +/- 0.7 1.4 +/- 0.4

-0.01 +/- 0.14 1295 +/-117

-0.4 +/- 2.0 3.0 +/- 2.3 1.6 +/- 1.9

-0.3 +/- 2.3 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 a See Introduction.

11

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES (Monthly Collections)

Sample Description and Concentration (pCVL)

Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-1 34 Cs-1 37 Ba-La-140 Other Gammasa Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-1 34 Cs-1 37 Ba-La-140 Other Gammasa E-1I Funk Dairy Farm 07-07-04 08-04-04 EMI-3481 EMI-4284 0.5 + 0.9

-0.5 +/- 0.7 0.6 +/- 0.4 1.1 +/- 0.4 0.09 +/-0.19 0.06 +/-0.13 1486 +/-115 1421 +/-89 1.2+/-2.1 0.3+/-1.8

-0.4 +/- 2.5 0.7 +/- 1.7 2.1 +/-1.9 0.5 +/-1.0 0.4 +/-1.8 1.0 +/-1.8 10-06-04 11-03-04 EMI-5738 EMI-6517 0.3 +/- 0.7 0.1 +/- 0.6 1.6 +/- 0.4

1. +/- 0.4

-0.09 +/- 0.13

-0.27 +/- 0.12 1355 +/-118 1597 +/-97

-0.3 +/- 2.5

-0.1 +/- 2.0

-1.9 +/- 2.6

-1.9 +/-1.9

-1.5 +/- 2.3

-2.1 +/-1.9

-1.4 +/- 2.6 0.1 +/-1.7 09-01-04 EMI-4925

-0.2 +/- 0.9 1.3 +/-0.4

-0.09 +/- 0.16 1369 +/-116

-1.3 +/-2.6 2.2 +/-2.4 2.2 +/-1.6

-0.7 +/- 2.3 12-01-04 EMI-7062,3

-0.8 +/- 0.6 1.1 +/-0.3 0.09 +/- 0.13 1548 +/-91

-1.2 +/-2.8

-1.0 +/-2.7

-1.6 +/- 1.9 1.7 +/- 2.7 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 a See Introduction.

.12

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES (Monthly Collections)

Sample Description and Concentration (pCVL)

Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-1 34 Cs-1 37 Ba-La-1 40 Other Gammasa Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 Cs-1 37 Ba-La-1 40 Other Gammasa 01-07-04 EMI-78 0.1 +/-1.0 1.8 +/-0.4 0.06 +/- 0.14 1400 +/- 115

-0.6 +/- 2.6 2.3 +/- 2.2 2.8 +/- 1.9 0.8 +/- 2.1 04-07-04 EMI-1503 0.3 +/- 0.6 0.7 +/- 0.3 0.01 +/-0.16 1426 +/-117 0.8 +/-2.4

-1.0 +/-2.5 0.4 +/-1.9 1.8 +/-2.5 E-40 Barta 02-04-04 EMI-460

-0.6 +/- 0.8 1.6 +/- 0.4

-0.14 +/-0.16 1328 +/- 103 1.6 +/- 2.4 1.3 +/-2.5 0.5 +/- 1.7 0.8 +/- 1.9 05-05-04 EMI-2211 0.4 +/- 0.8 0.6 +/- 0.3

-0.06 +/- 0.19 1483 +/-114

-0.2 +/- 2.5 0.2 +/- 2.2 2.3 +/- 2.2

-0.4 +/-1.9 03-03-04 EMI-939

-0.1 +/-0.6 1.2 +/- 0.4 0.07 +/- 0.16 1344 +/-116 2.4 +/- 2.2 0.8 +/- 2.7

-2.2 +/-2.1 0.4 +/-2.2 06-02-04 EMI-2712

-0.1 +/-0.7 1.5 +/- 0.4

-0.23 +/- 0.17 1356 +/-120 2.7 +/-2.3

-0.1 +/-2.1 1.8 +/- 1.3

-0.3 +/- 2.5 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 a See Introduction.

13

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES (Monthly Collections)

Sample Description and Concentration (pCi/L)

Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-1 34 Cs-1 37 Ba-La-140 Other Gammasa Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-1 34 Cs-1 37 Ba-La-140 Other Gammasa 07-07-04 EMI-3483

-0.6 +/- 1.2 1.5 +/- 0.5 0.14 +/- 0.15 1349 +121

-0.3 +/- 2.2 0.7 +/- 2.2

-0.3 +/- 1.7 1.2 +/- 2.3 10-06-04 EMI-5740

-0.6 +/- 0.8 1.6 + 0.5 0.06 + 0.15 1277 +/- 108 2.6 + 2.7 1.7 +/- 2.7 1.5 +/- 2.3 3.1 +/-2.2 E-40 Barta 08-04-04 EMI-4286,7

-0.5 +/- 0.7 1.6 +/- 0.3 0.10 +0.15 1420 +/-t 56 0.4 +/- 1.7 1.2 +/- 1.6

-3.3 + 1.5

-0.2 +/- 1.5 11-03-04 EMI-6519

-0.1 +/-0.6 1.3 +/- 0.4

-0.19 +/- 0.16 1372 +112 0.8 +/-2.2 3.8 +/-2.0 2.9 +/- 1.6 1.6 +/- 1.8 09-01-04 EMI-4928

-1.0 +/- 1.1 2.1 +/-0.6 0.10 +/-0.18 1382 +/- 126

-1.0 +/- 2.4 2.7 +/-2.4

-2.4 +/- 2.7 2.3 +/- 2.8 12-01-04 EMI-7065

-0.4 +/- 0.6 1.4 +/- 0.4 0.00 +/- 0.13 1426 +/-119

-2.3 +/- 2.6 1.2 +/- 2.3

-1.2 +/- 2.1 1.9 +/- 2.2 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 a See Introduction.

14

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES (Monthly Collections)

Sample Description and Concentration (pCiVL)

E-21 Strutz Dairv Farm Required LLD Collection Date Lab Code Sr-89 Sr-90 01-07-04 EMI-79,80 0.1 +/-0.7 1.0

0.2 02-04-04 EMI-461 0.3 +/- 0.6 0.6 +/- 0.3 03-04-04 EMI-940 0.1 +/-0.5 0.7 +/- 0.3 5.0 1.0 1-131 0.06 +/- 0.16 K-40 Cs-1 34 Cs-1 37 Ba-La-1 40 Other Gammas" 1418 +/- 85 0.4 +/-2.6

-0.7 +/- 2.3

-2.3 +/-1.8 2.8 +/-2.5

-0.03 +/- 0.15 1287 +/-110 2.4 +/-2.1 0.2 +/- 2.1 0.3 +/- 2.0 0.5 +/-1.8

-0.03 +/- 0.14 1402 +/- 130 2.6 +/- 2.5 3.0 +/- 2.5

-3.4 +/-2.4

-0.4 +/- 2.5 0.5 5.0 5.0 5.0 15.0 Required LLD Collection Date Lab Code Sr-89 Sr-90 04-07-04 EMI-1504 0.0 +/- 0.7 1.4 +/- 0.4 05-05-04 EMI-2212 0.1 +/-0.7 1.0 +/- 0.4 06-02-04 EMI-2711 0.2 +/- 0.5 0.4 +/- 0.3 5.0 1.0 1-131

-0.04 +/- 0.16 0.01 +/- 0.18

-0.16 +/- 0.17 0.5 K-40 Cs-134 Cs-1 37 Ba-La-140 Other Gammasa 1325 1.5 1.0

-0.6

+/- 101

+/-2.5

+/-2.0

+/-1.6

+/-1.6 1333 +/-118 2.1 +/-2.3 0.4 +/- 2.2

-1.2 +/-2.1 1.4 +/- 1.5 1317 +/-109

-0.9 +/-2.3

-1.0 +/- 2.6 0.5 +/-1.9

-1.5 +/-2.3 5.0 5.0 5.0 15.0 a See Introduction.

15

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN MILK SAMPLES (Monthly Collections)

Sample Description and Concentration (pCVL)

E-21 Strutz Dairv Farm Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-1 34 Cs-1 37 Ba-La-140 Other Gammas' Collection Date Lab Code Sr-89 Sr-90 1-131 K-40 Cs-134 Cs-1 37 Ba-La-140 Other Gammasa a See Introduction.

07-07-04 EMI-3482

-0.5

1.0 0.9 t 0.5 0.07 +/-0.15 1397 +/-110 1.0 +/-2.4 2.4 +/- 2.3

-2.7 +/-2.1 0.9 +/-2.0 10-06-04 EMI-5739

-0.1 +/-0.8 0.6 +/-0.4 0.13 t0.20 1428 +/-111 0.4 +/- 2.3 3.2 +/- 2.4

-2.9 +/- 1.9 0.3 +/-2.3 08-04-04 EMI-4285

-0.5 +/- 0.6 0.8 +/-0.3 0.09 +/- 0.14 1318 +/-88 2.4 +/-1.8

-1.1 +/-1.6 2.9 +/-1.3 0.1 +/-1.9 11-03-04 EMI-6518 0.4 +/- 0.6 0.6 +/- 0.4

-0.28 +/- 0.18 1400 +/-101 1.5 +/-2.4 5.5 +/-2.1

-0.9 +/-2.1

-0.5 +/- 2.0 09-01-04 EMI-4926,7

-0.2 +/- 0.8 1.8 +/- 0.6

-0.12 +/- 0.18 1301 +/-82

-0.2 +/- 2.6

-0.2 +/- 2.2

-0.8 +/- 1.9 1.0 +/- 1.9 12-01-04 EMI-7064 0.1 +/-0.5 0.5 +/- 0.3 0.10 +/- 0.14 1469 +/-117 0.6 +/-2.9 1.0 +/-2.8 0.7 +/-2.3

-2.9 +/-2.9 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 Required LLD 5.0 1.0 0.5 5.0 5.0 5.0 15.0 16

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN WELL WATER SAMPLES, E-10 (Quarterly Collections) 1st Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

Req.

LLD Collection Date NSb 04-13-04 07-14-04 10-13-04 Lab Code EWW-1668 EWW-3858 EWW-6042c Gross Beta 3.5 +/-1.9 0.9 +/- 1.5 16.5 +/-2.2 4.0 H-3

-9.4 +/- 84.6 110.8 +/- 88.9 7.6 +/- 79.4 500 Sr-89 0.2 +/- 0.5 0.1 +/-0.6 0.4 +/- 0.5 5.0 Sr-90

-0.1 +/- 0.3 0.2 +/- 0.3

-0.2 +/- 0.3 1.0 1-131

-0.05 +/- 0.15 0.16 +/- 0.24

-0.02 +/- 0.20 0.5 Mn-54

-0.3 +/-1.9 0.3 +/- 3.7

-0.7 +/- 2.8 10 Fe-59 0.4 +/-4.0

-3.2 +/- 4.9 4.3 +/- 6.4 30 Co-58

-0.5 +/-2.0

-1.9 +/- 3.9

-3.9 +/- 3.6 10 Co-60

-2.9 +/-2.0

-1.8 +/-3.7 0.5 +/-4.4 10 Zn-65

-0.7 +/- 3.9

-1.5 +/- 6.9 0.7 +/- 6.6 30 Zr-Nb-95

-4.3 +/- 2.8 1.1 +/- 3.6

-4.9 +/- 3.5 15 Cs-134

-1.8 +/-2.5

-0.3 +/-4.1

-0.9 +/-3.3 10 Cs-137

-0.6 +/-2.6

-2.1 +/- 3.5 0.6 +/- 3.5 10 Ba-La-140

-2.5 +/- 8.4

-19.8 +/- 5.2 3.1 +/- 3.2 15 Other Gammasa 0.9 +/- 1.9 0.2 +/- 3.1 0.7 +/- 2.9 30 a Ru-1 03 b*NSu= No sample; sample not received.

c Gross beta repeated with a result of 15.9+/-3.8 pCi/L; sample had heavy total residue.

17

POINT BEACH Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes.

Location: E-01 (Meteorological Tower)

Collection: Monthly composites Units: pCUL Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-1 37 Ba-La-1 40 Other Gammasa ELW-256 01-15-04 2.8 t 0.7

-0.15 +/- 0.15

-10.7 +/- 19.7 1.4 +/- 1.7

-4.1 +/- 3.6 0.2 +/- 1.8 2.0 +/- 1.4

-4.2 +/- 4.5

-0.5 +/- 1.9 0.5 +/- 1.8

-2.1 +/- 2.2 0.4 +/- 2.1

-1.9 +/- 2.4 NSb ELW-1135 03-23-04 3.1 t 0.6

-0.08 t 0.14 11.9 t 16.2

-0.3 t 2.0

-2.0 +/- 3.9

-0.1 +/- 1.9

-0.4 +/- 1.7 0.5 t 3.9 0.1 +/-t 2.0 0.8 +/- 2.1 1.2 t 2.0 0.7 +/- 2.2

-2.0 +/- 2.3 ELW-1 678 04-13-04 2.6 0.01

-28.7

-0.7

-2.5 1.5

-0.3 0.3

-0.6 2.8 0.1 0.5 0.2

+/- 0.6

+/- 0.15

+/- 19.1

+/- 1.8

+/- 3.7

+/- 1.6

t 2.0

+/- 4.3

+/- 1.9

+/- 2.4

+/- 2.2

+/- 1.9

+/- 2.2 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-1 40 Other Gammas' ELW-2217 05-05-04 2.9 +/- 0.6 0.13 +/- 0.23 3.4 +/- 11.9

-0.3 +/- 1.5 0.8 +/- 2.3 0.2 +/- 1.2 0.1 +/- 1.7

-0.1 +/- 3.1

-1.5 +/- 1.2 1.3 +/- 1.5 1.3 +/- 1.5

-1.8 +/- 1.7

-0.1 +/- 1.4 ELW-3034 06-11-04 2.4 +/- 0.5

-0.28 +/- 0.22 4.7 +/- 26.4 2.0 +/- 3.3

-5.0 +/- 6.3 2.3 +/- 3.1

-2.1 +/- 4.4

-0.3 +/- 6.0

-2.9 +/- 2.8 1.5 +/- 3.4

-1.1 +/- 3.3

-5.5 +/- 4.3 0.3 +/- 2.9 ELW-3849,50 07-14-04 2.3 +/- 0.4

-0.41 +/- 0.23 2.3 +/- 16.6 0.5 +/- 1.7 1.2 +/- 3.1

-2.1

+/- 1.7

-0.1

+/- 1.6

-4.2 +/-t 7.3

-0.4 +/- 1.7 0.2 +/- 1.8

-1.8 +/- 1.8

-5.0 +/- 2.0

-1.3 +/- 2.0 ELW-4579 08-11-04 2.4 0.13

-4.8

-0.9 0.5

-2.3

-0.1

-3.0

-0.4 0.6

-0.1

-0.3 1.8

+/- 0.5

+/- 0.18

+/- 18.8

+/- 2.1

+/- 3.8

+/- 2.0

+/- 1.5

+/- 1.9

+/- 1.5

+/- 1.7

+/- 2.4

+/- 2.3

+/- 1.9 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-137 Ba-La-1 40 Other Gammasa ELW-5313 09-16-04 2.6 +/- 0.6

-0.16 +/- 0.17 45.4 +/- 27.2 2.2 +/- 3.9

-6.1 +/- 6.6 1.6 +/- 3.0 4.6 +/- 4.1 1.2 +/- 7.0 1.8 +/- 3.4 2.6 +/- 3.2 0.2 +/- 3.0

-13.3 +/- 5.0

-2.0 +/- 3.4 ELW-6038 10-13-04 2.3 +/- 0.6 0.07 +/- 0.16

-5.7 +/- 29.6 1.9 +/- 2.7

-1.7 +/- 6.9 1.1 +/- 3.4 1.3 +/- 4.4

-1.5 +/- 5.9 3.2 +/- 3.0 0.8 +/- 4.1 2.0 +/- 3.6 4.1 + 3.5

-1.6 +/- 3.6 ELW-6777 11-10-04 ELW-7242 12-08-04 2.3

-0.16 11.9 1.4 10.5

-0.8

-1.5

-0.8 2.9 0.7

-1.4

-3.1 1.3

+/- 0.6

+/- 0.19

+/- 25.9

+/- 3.7

+/- 5.7

+/- 3.5

+/- 3.7

+/- 8.9

+/- 3.1

+/- 4.1

+/- 3.4

+/- 4.7

+/- 3.3 2.6

-0.22

-13.7

-0.5

-1.4 1.5 0.6

-10.6

-0.2

-1.4 0.1

-7.0 4.0

+/- 0.6

+/- 0.16

+/- 19.7

+/- 2.1

+/- 4.2

+/- 1.8

+/- 2.1

+/- 4.6

+/- 2.0

+/- 2.5

+/- 2.3

+/- 2.2 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 a Ru-103 b ONSN = No sample; see Table 2.0, Listing of Missed Samples.

18

POINT BEACH Lake water, analyses for gross beta, iodine-1 31 and gamma emitting isotopes.

Location: E-05 (Two Creeks Park)

Collection: Monthly composites Units: pCiL Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Other gammas" ELW-257 01 04 3.1 +/-t 0.6 NSb

-0.01

-1.0 2.1

-2.8 0.9 0.3 0.4 0.5

-0.7 1.7

-0.1

-1.2

+/- 0.16

+ 17.1

+/- 1.6

+/- 3.4

+/- 1.4

+/- 1.3

+/- 2.9

+/- 2.0

+/- 2.3

+ 2.0

+/- 2.0 ELW-1136 03-23-04 3.0 +/- 0.6

-0.03 +/- 0.15

-8.1 +/- 17.8 1.0 +/- 1.8 2.0 +/- 2.8

-0.1 +/- 1.7

-0.8 +/- 1.5 0.9 +/- 3.3 1.8 +/- 1.8 0.7 +/- 1.9 1.6 +/- 1.9

-0.7 +/- 2.5

-1.8 +/- 2.0 2.7 0.23

-21.9 2.2

-4.2

-1.1

-1.2

-5.1

-1.2

-0.7

-0.9

-1.5

-2.5 ELW-1 679 04-13-04

+/- 0.5

+/- 0.26

+/- 26.4

+/- 2.8

+/- 6.1

+/- 3.3

+/- 3.4

+/- 6.7

+/- 3.3

+/- 3.8

+/- 3.4

+/- 3.9

+/- 2.9 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-1 37 Ba-La-1 40 Other Gammasa Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-1 37 Ba-La-1 40 Other Gammasa ELW-2218 05-05-04 2.2 +/- 0.5 0.00 +/- 0.22

-4.1 +/- 14.1

-0.1 +/- 1.2

-0.7 +/- 2.9 0.8 +/- 1.3 0.2 +/- 1.4

-4.8 +/- 3.2 0.3 +/- 3.1 1.0 +/- 1.5 0.5 +/- 1.6

-1.9 +/- 1.6

-0.2 +/- 1.6 ELW-5314 09-16-04 2.0 +/- 0.5 0.06 +/- 0.18 9.0 +/- 30.4 1.2 +/- 3.5 3.7 +/- 6.7 0.8 +/- 3.2

-0.9 +/- 3.5

-2.7 +/- 8.9

-0.5 +/- 3.1 2.7 +/- 3.4 1.3 +/- 3.6 2.7 +/- 3.3

-1.4 +/- 3.4 ELW-3035 06-11-04 2.9 +/- 0.6 0.01 +/- 0.26

-7.1 +/- 23.0 2.8 +/- 3.4 9.0 +/- 5.9

-2.5 +/- 4.1 0.1 +/- 4.5

-4.9 +/- 8.3

-0.7 +/- 3.8 1.3 +/- 3.4 1.5 +/- 2.8 6.1 +/- 3.3 1.4 +/- 3.1 ELW-6039 10-13-04 2.6 +/- 0.6 0.08 +/- 0.14

-6.2 +/- 14.4

-0.3 +/- 2.0 1.2 +/- 3.6

-0.4 +/- 2.1 2.7 +/- 2.3

-1.5 +/- 3.3

-0.4 +/- 1.9 0.4 +/- 2.3

-1.0 +/- 2.0 3.4 +/- 2.4 2.0 +/- 1.7 ELW-3851 07-14-04 ELW-4580 08-11-04 3.1

-0.09

-11.7

-2.6 4.3

-1.7 0.8

-0.3 2.0 0.7

-0.5

-3.6

-0.5

+/- 0.6

+/- 0.29

+/- 15.1

+/- 1.9

+/- 2.4

+/- 1.4

+/- 1.7

+/- 3.2 t 1.6

+/- 1.9 t 1.9

+/- 1.8

+/- 1.8 2.0

-0.05

-25.2 0.9

-6.6

-3.6 0.4 1.0 1.6

-2.5 0.8 6.6 1.1

+/- 0.5

+/- 0.18

+/- 27.3

+/- 3.1

+/- 6.7

+/- 2.9

+/- 3.8

+/- 7.8

+/- 3.5

+/- 4.2

+/- 3.1

+/- 3.6

+/- 3.1 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 ELW-6778 11-10-04 2.6 +/- 0.6 0.09 +/- 0.17 4.8 +/- 19.3 3.3 +/- 3.1 2.2 t 5.3 0.4 +/-t 2.6

-1.0 t 2.0 3.0 +/- 6.1 2.7 +/- 2.4 1.2 +/-t 3.2 0.8 +/- 3.4 3.5 +/- 2.1 0.3 +/- 2.3 ELW-7243c 12-08-04 7.3 0.03 16.8 0.3

-4.6 0.7

-1.6

-6.3

-1.5 0.9

-0.5

-0.8 0.7 t 0.8

+/- 0.17 t 20.3 t 2.4

+/- 4.4

+/- 2.2 t 2.2 t 5.8

+/-e 2.5

+/- 2.6 t 2.7

+/- 2.6

+/- 2.5 a Ru-103 b 'NS' = No sample; see Table 2.0, Listing of Missed Samples.

c Gross beta repeated with a result of 8.2+/-0.8 pCVL.

19

POINT BEACH Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes.

Location: E-06 (Coast Guard Station)

Collection: Monthly composites Units: pCi/L Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-137 Ba-La-140 Other Gammasa ELW-258 01-15-04 2.6 +/- 0.6 0.08 +/- 0.18 7.6 +/- 15.2

-0.1 +/- 1.7

-0.4 +/- 3.3 1.1 +/- 1.5

-0.2 +/- 1.6 0.5 +/- 4.0

-1.5 +/- 1.9 1.2 +/- 2.0 0.1 +/- 1.7 0.3 + 1.9

-4.6 +/- 2.2 NSb ELW-1137 03-23-04 3.8 +/- 0.6

-0.23 +/- 0.14 20.8 +/- 23.5 1.0 +/- 2.7 2.4 +/- 6.8

-1.6 +/- 3.5 1.2 +/- 3.9

-1.3 +/- 7.0

-0.7 +/- 3.0

-2.2 +/- 4.0 1.5 +/- 2.9

-4.1 +/- 4.9

-3.6 +/- 2.7 ELW-1680,1 04-13-04 2.7 +/- 0.5

-0.07 +/- 0.22 6.9 +/- 18.1

-0.1 +/- 2.2 0.9 +/- 3.3

-0.7 +/- 1.6

-1.0 +/- 2.3

-6.9 +/- 4.3 0.6 +/- 2.2

-2.0 +/- 2.0 0.9 +/- 2.1

-4.5 +/- 2.2

-1.2 +/- 2.1 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-i 40 Other Gammasa Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-137 Ba-La-1 40 Other Gammasa ELW-2219 05-05-04 2.5 +/- 0.6

-0.17 t 0.21 4.7 t 18.6

-0.4 t 2.1

-4.0 +/- 3.0

-0.6 +/- 1.8 0.2 +/- 2.0

-0.8 +/- 4.1

-0.7 t 1.8

-0.2 +/-t 1.9 0.9 t 2.2

-0.9 +/- 2.4 0.2 +/- 2.0 ELW-5315 09-16-04

2.9 +/- 0.6

-0.03 +/- 0.18 7.0 +/- 19.6

-0.4 +/- 1.7 0.9 +/- 3.4

-0.4 +/- 2.0 0.4 +/- 2.8

-2.1 +/- 4.6.

2.2 +/- 2.2 2.2 +/- 2.2

-2.3 +/- 2.3

-0.6 +/- 2.6

-0.2 +/- 2.5 ELW-3036 06-11-04 1.9 +/- 0.5

-0.14 +/- 0.26

-15.2 +/- 29.3 1.7,+/- 4.0 5.5 +/- 5.8 2.6 +/- 3.6 0.4 +/- 3.1

-0.8 +/- 7.2 1.2 +/- 3.4 0.3 +/- 4.1

-1.4 +/- 3.5

-4.7 +/- 4.9

-2.9 +/- 3.3 ELW-6040 10-13-04 1.9 +/- 0.6

-0.23 +/- 0.18 9.5 +/- 32.9 1.8 +/- 3.3 4.6 +/- 6.0

-1.4 +/- 3.6 1.1 +/-3.7

-2.0 +/- 7.4 1.4 +/- 3.9

-2.4 +/- 4.6 1.7 +/- 3.5

-12.0 +/- 3.6 0.2 +/- 3.6 ELW-3852 07-14-04 1.7 +/- 0.5

-0.11 +/- 0.20 3.3 +/- 22.0 0.1 t 2.8

-4.5 t 6.0 1.7 +/- 2.6 2.8 +/- 3.3

-4.8 +/- 5.2 0.7 +/- 2.6 1.8 +/- 3.1

-1.3 +/- 2.7

-0.4 +/- 3.0

-1.1 +/- 2.4 ELW-6779 11-10-04 2.7 +/- 0.6

-0.09 +/- 0.15 15.5 +/- 24.4

-1.6 +/- 2.8 1.4 +/- 6.7

-1.3 +/- 3.2 1.5 +/- 3.4

-3.4 +/- 6.6 1.7 +/- 3.4

-1.2 +/- 3.6 1.4 +/- 3.1

-2.5 5 5.0

-3.7 +/- 2.9 ELW-4577 08-12-04 2.6 +/- 0.6 0.02 +/- 0.15

-10.4 +/- 20.9 1.1

+/- 2.7

-4.1 +/- 4.9

-0.4 +/- 2.4 0.3 +/- 3.1

-1.9 +/- 6.5 0.9 +/- 2.6

-2.3 +/- 3.5

-0.1 +/- 3.7

-8.2 +/- 3.2

-0.1 +/- 2.6 ELW-7244 12-08-04 2.2 +/- 0.5 0.16 +/- 0.17

-4.2 +/- 19.0 0.7 +/- 2.1 1.2 +/- 3.2

-4.0 +/- 2.5

-3.3 +/- 2.1

-3.5 +/- 4.3

-1.7 +/- 2.2 0.2 +/- 2.2 0.2 +/- 2.1 3.8 +/- 2.0 1.7 +/- 2.3 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 a Ru-103 b NS" = No sample; see Table 2.0, Listing of Missed Samples.

20

POINT BEACH Lake water, analyses for gross beta, io'dine-131 and gamma emitting isoi6pes.

Location: E-33 (Nature Conservancy)

Collection: Monthly composites Units: pCUL Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-137 Ba-La-1 40 Other Gammasa ELW-259 01-15-04 3.5 +/- 0.6

-0.02 +/- 0.19

-1.1 +/- 19.0

-0.8 +/- 2.8 0.3 +/- 4.5 0.2 +/- 2.8

-0.7 +/- 2.6

-0.6 +/- 4.8

-2.1 +/- 2.4

-0.2 +/- 3.3 1.0 +/- 3.2

-0.6 +/- 4.4 0.0 +/- 2.4 NSb ELW-1138 03-23-04 3.5 +/- 0.6

-0.07 +/- 0.13 7.8 +/- 26.1

-2.0 +/- 3.3

-2.5 +/- 6.8 1.7 +/- 3.5 0.4 +/- 3.9 2.0 +/- 5.2

-1.6 +/- 3.2 0.6 +/- 4.0

-0.6 +/- 2.9 1.3 +/- 3.0

-0.6 +/- 3.7 ELW-1 682 04-13-04 2.6

-0.13 10.9

-2.2 0.3 0.2 0.3

-3.5 2.8

-2.6

-1.2

-0.3

-0.7

+/- 0.6

+/- 0.20

+/- 18.3

+/- 2.0

+/- 3.0

+/- 1.6

+/- 3.8

+/- 1.7

+/- 2.2

+/- 2.0

+/- 2.2

1.9 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-137 Ba-La-140 Other Gammasa ELW-2220 05-05-04 3.4 +/- 0.6

-0.15 +/- 0.20

-4.3 +/- 12.1

-0.8 t 1.3

-1.3 t 2.4 0.8 +/- 1.2

-0.1 +/- 1.2

-1.2 +/- 2.3 0.7 t 1.3

-1.6 t 1.5 1.8 t 1.3

-1.3 +/- 1.5

-0.6 +/-t 1.5 ELW-3037 06-11-04 4.9

0.7 0.13

0.26

-12.6 +/- 30.0 3.9 +/- 3.3 1.8 +/- 2.8 0.4 +/- 2.8 1.8 +/- 2.9 0.7 +/- 6.6

-0.2 +/- 2.9

-2.0 +/- 4.0 1.5 +/- 3.2 0.9 +/- 4.6

-1.4 +/- 3.4 ELW-3853 07-14-04 1.8 +/- 0.5 0.14 +/- 0.21

-24.4 +/- 22.8 2.6 +/- 3.0 4.5 +/- 5.8

-4.1 +/- 3.0 2.4 +/- 2.6 4.3 +/- 5.1 2.3 +/- 2.9

-1.0 +/- 3.2

-1.1 +/- 2.7

-15.3 +/- 4.2

-3.1 +/- 2.9 ELW-4578 08-12-04 4.2 +/-t 0.6 0.26 +/- 0.17

-0.7 +/- 17.7

-2.4 +/- 2.2

-0.3 :+/- 2.9

-0.4 +/- 1.7 0.1 +/- 2.0

-0.7 +/- 4.3 0.1 +/- 1.6

-3.1 t 2.3

-0.3 + 2.1

-0.4 +/-t 1.9

-0.8 +/- 2.3 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 Lab Code Date Collected Gross beta 1-131 Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-1 37 Ba-La-1 40 Other Gammasa ELW-5316, 7 09-i16-04 2.7 +/- 0.4

-0.13 +/- 0.16 4.1 +/- 17.6

-0.2 +/- 1.9

-2.2 +/- 4.2

-2.6 +/- 2.8

-0.3 +/- 1.6

-1.8 +/- 4.5 1.8 +/- 2.1 0.3 +/- 1.9

-0.4 +/- 1.9

-2.9 +/- 2.0

-1.3 +/- 1.9 ELW-6041 10-13-04 1.6

0.5

-0.13 +/- 0.20

-3.9 +/- 11.7

-0.4 +/- 1.4

-0.1 4-2.5

-0.2 +/- 1.2 0.7 +/- 1.2

-0.2 +/- 2.6

-1.5 +/- 1.4

-1.8 +/-t 1.5

-0.6 +/- 1.4

-6.1 +/- 1.6

-0.5 +/- 1.3 ELW-6780 11-10-04 2.6 +/- 0.6

-0.16 +/-t 0.15

-7.4 +/- 17.2

-1.2 t 2.0

-5.6 +/- 4.1

-1.6 t 2.0 0.6 +/- 1.7

-1.8

4.9

-3.0 +/- 1.8

-1.1 +/- 2.1 0.0 +/- 2.2 2.0 t 2.3

-0.7 +/- 2.0 ELW-7245 12-08-04 5.1

-0.11

-18.7 1.4

-0.4

-5.3 0.7

-6.4

-1.3 3.9 0.6

-4.4

-1.2

+/- 0.7

+/- 0.14

+/- 30.0

+/- 3.1

+/- 4.6

+/- 3.1

+/- 3.2

+/- 6.1

+/- 3.2

+/- 4.1

+/- 3.2

+/- 3.8

+/- 3.1 Req. LLD 4.0 0.5 10 30 10 10 30 15 10 10 15 30 a Ru-103 bNNS" = No sample; see Table 2.0, Listing of Missed Samples.

21

POINT BEACH Lake water, analyses for tritium, strontium-89 and strontium-90.

Collection: Quarterly composites of weekly grab samples Units: pCVL Location E-01 (Meteorological Tower)

Period 1 st Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

Lab Code ELW-1215 ELW-3178 ELW-5615 ELW-7594 H-3 118 +/-84 189 +/-86 102 +/-89 139 +/-89 Sr-89

-0.17 +/- 0.53

-1.01 +/- 0.78

-0.90 +/- 1.14 0.60 +/- 0.79 Sr-90 0.49 +/-0.32 1.09 +/-0.42 1.01 +/-0.62 0.48 +/-0.32 Location E-05 (Two Creeks Park)

Period 1 st Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

Lab Code ELW-1216 ELW-3179 ELW-5616 ELW-7595a H-3 60 +/-82 217 +/-87 40 +/-86 1186 +/-126 Sr-89

-0.30 +/- 0.56 0.46 +/- 0.73

-0.34 +/-1.08 0.47 +/- 0.84 Sr-90 0.55 +/- 0.33 0.73 +/- 0.34 0.74 +/- 0.55 0.42 +/- 0.35 Location E-06 (Coast Guard Station)

Period 1 st Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

Lab Code ELW-1217 ELW-3180 ELW-5617 ELW-7596 H-3 82 +/-83 253 +/-88 109 +/-89 56 +/-86 Sr-89

-0.12 +/-0.48

-0.26 +/-0.65

-1.04 +/-1.15 0.11 +/-0.85 Sr-90 0.49 +/-0.29 0.52 +/-0.33 1.12 +/-0.62 0.38 +/-0.37 Location E-33 (Nature Conservancy)

Period 1 st Qtr.

2nd Qtr.

3rd Qtr.

4th Qtr.

Lab Code ELW-1218 ELW-3181 ELW-5618 ELW-7597 H-3 123 +/-84 146 +/-84 47 +/-86 118 +/-88 Sr-89 0.04 +/-0.52 0.50 +/-0.63 0.44 +/-0.97

-0.52 +/-0.79 Sr-90 0.40 +/-0.31 0.22 +/-0.29 0.51 +/-0.47 0.64 +/-0.33 aTritium repeated with a result of 1144+/-127 pCUL.

Note: pages 23 and 24 are intentionally left out.

22

POINT BEACH NUCLEAR PLANT Fish, analyses for gross beta and gamma emitting Isotopes.

Location: E-13 Collection: 3x / year Units: pClg wet Sample Description and Concentration Required LLD Collection Date Lab Code Type Ratio (wet/dry wt.)

Gross Beta 03-12-04 EF-1 021 Rainbow Trout 1.80 3.31 +/- 0.11 03-12-04 EF-1 022 Brown Trout 2.80 3.97

0.11 03-12-04 EF-1 023 Brown Trout 1.96 3.36 +/-t 0.09 03-12-04 EF-1 024 Brown Trout 2.10 3.81 +/- 0.10 0.5 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Ru-1 03 Cs-1 34 Cs-137 3.03 +/- 0.44 0.009 +/- 0.010 0.004 +/-t 0.017 0.004 +/- 0.007 0.001 +/-t 0.009 0.003 +/- 0.024

-0.004 +/- 0.007 0.001 +/- 0.010 0.023 +/- 0.013 3.15 +/-0.68 0.009 t 0.021

-0.003 +/-t 0.039

-0.007 t0.017

-0.015 +/- 0.020

-0.035 +/- 0.046

-0.018 +/- 0.019

-0.007 +/-t 0.024 0.017 +/- 0.024 3.16 +/-t 0.42 0.003 +/- 0.010

-0.005 +/- 0.022

-0.001 +/- 0.008 0.007 +/- 0.011 0.009 +/- 0.022 0.005 +/- 0.008 0.008 +/- 0.011 0.031 +/- 0.013 3.08 +/- 0.44

-0.004 +/- 0.007

-0.009 +/- 0.022 0.009 +/- 0.008 0.011 +/-0.012 0.001 +/- 0.019

-0.004 +/- 0.008 0.001 +/- 0.009 0.074 +/- 0.026 0.13 0.26 0.13 0.13 0.26 0.5 0.13 0.15 Collection Date Lab Code Type Ratio (wet/dry wt.)

Gross Beta K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Ru-1 03 Cs-134 Cs-1 37 08-12-04 EF-4512 Burbot 4.37 2.62 +/- 0.06 2.00 +/- 0.48 0.009 +/- 0.011

-0.014 +/- 0.025 0.008 +/- 0.010 0.007 +/- 0.014

-0.004 +/- 0.033

-0.003 +/- 0.009

-0.004 +/- 0.013 0.071 +/- 0.033 08-12-04 EF-4513 Burbot 5.09 2.60 +/- 0.08 1.72 +/- 0.51 0.002 +/- 0.012 0.032 +/- 0.028

-0.025 +/- 0.014

-0.001 +/- 0.010

-0.028 +/- 0.025 0.006 +/- 0.010

-0.003 +/-0.013 0.026 +/- 0.018 08-12-04 EF-4514 Lake Trout 2.14 2.80 +/- 0.09 2.54 +/- 0.48 0.011 +/- 0.013 0.058 +/- 0.024

-0.004 +/- 0.014 0.007 +/- 0.013 0.014 +/- 0.027 0.003 +/- 0.011 0.009 +/-0.014 0.052 +/- 0.026 10-03-04 EF-7209 Lake Trout 2.79 3.38 +/- 0.12 2.76 +/- 0.24 0.007 +/- 0.005 0.012 +/- 0.010 0.007 +/- 0.005 0.001 +/- 0.004

-0.026 +/- 0.014

-0.033 +/- 0.005 0.002 +/- 0.005 0.046 +/- 0.014 0.5 0.13 0.26 0.13 0.13 0.26 0.5 0.13 0.15 25

POINT BEACH NUCTLEAR PLANT Fish, analyses for gross beta and gamma emitting isotopes.

Location: E-13 Collection: 3x / year Units: pCiVL Sample Description and Concentration (pC/g wet)

Required LLD Collection Date Lab Code Type Ratio (wet/dry wt.)

Gross Beta 09-29-04 EF-721 0 Lake Trout 2.39 4.70

0.12 09-29-04 EF-7211,12 Lake Trout 2.15 5.77 +/-0.13 0.5 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Ru-1 03 Cs-1 34 Cs-1 37 2.86 +/- 0.25 0.000 +/- 0.006 0.013 +/- 0.012 0.005 +/- 0.006 0.002 +/- 0.006

-0.015 +/- 0.015 0.037 +/- 0.005

-0.003 t 0.007 0.056 +/- 0.014 2.92 +/-0.19

-0.002 +/- 0.005 0.002 t 0.011

-0.001 +/- 0.005 0.001 +/-0.006

-0.014 +/- 0.014

-0.005 +/- 0.005 0.003 +/- 0.006 0.047 +/- 0.011 0.13 0.26 0.13 0.13 0.26 0.5 0.13 0.15 NOTE: Page 27 is intentionally left out.

26

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN SHORELINE SEDIMENT SAMPLES (Semiannual Collections)

Sample Description and Concentration (pCVg dry)

Collection Date Lab Code 04-13-04 ESS-1 669 04-13-04 ESS-1 670 E-05 04-13-04 ESS-1 671 Required LLD Location E-01 E-06 Gross Beta Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 9.92 +/- 1.48 0.027 + 0.053 3.83 +/- 0.33 0.011 +/- 0.008 0.033 + 0.014 0.08 +/- 0.018 0.08 :+/- 0.028 0.36 + 0.144 0.06 +/-k 0.036 8.78 +/- 1.90 0.044 +/- 0.062 7.42 +/- 0.42 0.026 +/- 0.009 0.054 +/-t 0.016 0.14 +/- 0.020 0.11 +/- 0.028 0.28 +/- 0.182 0.19 + 0.071 7.86 +/- 1.87 0.123 +/-0.077 5.95 +/- 0.55 0.015 +/- 0.013 0.075 +/- 0.028 0.16 +/- 0.024 0.13 +/-t 0.035 0.41 +/-0.233 0.25 +/- 0.089 2.0 0.15 Collection Date Lab Code Location 04-13-04 ESS-1 672 04-13-04 ESS-1 673 E-33 E-12 Gross Beta Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 5.88 +/- 1.83 0.079 +/- 0.052 4.62 +/- 0.34 0.021 +/- 0.012 0.048 +/- 0.013 0.14 +/- 0.020 0.16 +/- 0.027 0.32 +/- 0.171 0.15 +/- 0.043 11.54 +/- 2.15 0.060 +/- 0.066 9.18 +/- 0.67 0.016 +/- 0.012 0.038 +/- 0.021 0.09 +/- 0.020 0.14 +/- 0.045 0.29 +/-0.158 0.12 +/- 0.053 2.0 0.15 28

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN SHORELINE SEDIMENT SAMPLES (Semiannual Collections)

Sample Description and Concentration (pCVg dry)

Collection Date Lab Code 10-13-04 ESS-6043 10-13-04 ESS-6044 E-05 10-13-04 ESS-6045 Required LLD Location E-01 E-06 Gross Beta Be-7 K-40 Cs-137 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 6.89 + 1.96

-0.007 +/- 0.061 5.81

0.47 0.007 +/-t 0.010 0.042 +/- 0.019 0.12 +/-0.019 0.11 +/- 0.026 0.33 +/- 0.15 0.17 +0.066 9.88 +2.01 0.003 + 0.060 7.85 +/- 0.55 0.016 +/- 0.009 0.046 +/- 0.021 0.12 +/- 0.018 0.16 +/- 0.040 0.29 + 0.17 0.09 +/- 0.045 8.40 +/- 1.90

-0.022 +/- 0.044 8.24 +/-t 0.53 0.030 +/- 0.016 0.038 +/- 0.020 0.12 +/-0.019 0.12 t 0.028 0.12 +/-0.13 0.16 +/- 0.060 2.0 0.15 Collection Date Lab Code 10-13-04 ESS-6046,7 10-13-04 ESS-6048 E-33 Location E-1 2 Gross Beta 8.75 t 1.27 12.15

1.45 2.0 Be-7 K-40 Cs-137 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 0.046 5.77 0.022 0.041 0.16 0.12 0.29 0.16

0.045

+/- 0.29

+/- 0.008

+/- 0.010

+/- 0.030

+/- 0.018

+/- 0.11

+/- 0.035 0.080 +/-t 0.065 10.14 +/-0.59 0.058 +/- 0.021 0.045 +/- 0.017

0.10 +/- 0.020 0.14 +/- 0.038 0.28 +/- 0.15 0.14 +/- 0.075 0.15 29

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN SOIL SAMPLES (Semiannual Collections)

Sample Description and Concentration (pCi/g dry)

Collection Date Lab Code f

Location Gross Beta Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 05-26-04 ESO-2572 E-01 25.59

2.65

-0.01 +/- 0.09 15.64 +/- 1.03 0.19 +/-0.04 0.16 +/- 0.04 0.46 +/- 0.04 0.38 +/- 0.06 1.05 +/-t 0.33 0.68 +/- 0.17 05-26-04 ESO-2573 E-02 31.25 +/- 2.89

-0.04 +/- 0.09 23.01 +/- 0.95 0.12 +/- 0.03 0.23 +/- 0.04 0.70 +/- 0.04 0.53 +/- 0.05 1.20 +/- 0.32 0.76 +/- 0.11 05-26-04 ESO-2574 E-03 18.76 +/-2.29 0.15 +/-0.10 11.03 +/- 0.83 0.02 +/- 0.02 0.09 +/- 0.03 0.22 +/- 0.03 0.18 +/- 0.04 0.60 +/- 0.29 0.32 +/- 0.11 Required LLD 2.0 0.15 Collection Date Lab Code Location Gross Beta Be-7 K-40 Cs-1 37 TI-208

.Pb-212 Bi-214 Ra-226 Ac-228 05-26-04 ESO-2575 E-04 24.82 +/- 2.63 0.04 +/- 0.10 17.25 +/- 1.05 0.16 +/- 0.04 0.16 +/- 0.04 0.44 +/- 0.04 0.34 +/- 0.07 0.67 +/- 0.30 0.45 +/- 0.11 05-26-04 ESO-2576 E-06 16.92 +/- 2.25 0.05 +/- 0.10 11.81 +/- 0.77 0.10 +/- 0.03 0.11 +/- 0.03 0.36 +/- 0.04 0.29 +/- 0.05 0.55 +/- 0.29 0.42 +/- 0.10 05-26-04 ESO-2577 E-08 17.45 +/-2.32

-0.06 +/- 0.07 11.62 +/- 0.76 0.06 +/- 0.02 0.10 +/- 0.03 0.22 +/- 0.03 0.22 +/- 0.04 0.53 +/- 0.22 0.32 +/- 0.08 2.0 0.15 Collection Date Lab Code Location Gross Beta Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 05-26-04 ESO-2578,9 E-09 28.40 +/- 2.21 0.02 +/-0.13 19.17 +/- 0.65 0.18 +/- 0.03 0.19 +/- 0.03 0.53 +/- 0.03 0.44 +/- 0.04 1.01 +/-0.23 0.55 +/- 0.07 05-26-04 ESO-2580 E-20 23.82 +/- 2.78 0.09 +/- 0.09 16.59 +/- 0.88 0.43 + 0.05 0.14 +/- 0.03 0.52 + 0.11 0.38 +/- 0.06 0.60 +/- 0.30 0.51 +/-0.10 2.0 0.15 30

POTNT BEACH NUCLEAR PLANT RADIOACTIVITY IN SOIL SAMPLES (Semiannual Collections)

Sample Description and Concentration (pCig dry)

Collection Date Lab Code Location Gross Beta Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214

.Ra-226 Ac-228 10-29-04 ESO-6580 E-01 10-29-04 ESO-6581 E-02 10-29-04 ESO-6582 E-03 Required LLD 27.08

2.73 0.16 +/-0.10 17.85

0.94 0.15 +0.03 0.20 +/- 0.04 0.80 +/- 0.13 0.43 +/- 0.08 1.27 +/- 0.46 0.95 +/- 0.14 28.47 +/- 2.77 0.16 +/- 0.10 21.95 +/- 1.00 0.14 +/-t 0.04 0.21 +/- 0.04 0.73 +/- 0.12 0.52 +/- 0.06 0.74 +/-t 0.34 0.74 +/- 0.15 27.91 +/- 2.78 0.260 +/- 0.10 18.84 +/- 0.91 0.16 + 0.04 0.18 +/- 0.03 0.64 + 0.11 0.46 +/- 0.06 0.86 +/- 0.31 0.64 +/-t 0.14 2.0 0.15 Collection Date Lab Code Location Gross Beta Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 10-29-04 ESO-6583 E-04 28.22 +/- 2.73 0.180 +/- 0.16 19.54 +/- 1.15 0.22 +/- 0.07 0.20 +/- 0.04 0.61 +/- 0.05 0.41 +/- 0.06 1.15 + 0.42 0.67 +/- 0.16 10-29-04 ESO-6584 E-06 25.62 + 2.67 0.18 +/-0.13 18.46 +/- 1.13 0.14 +/- 0.04 0.21 +/- 0.04 0.54 +/- 0.04 0.47 +/- 0.09 0.98 +/-t 0.32 0.63

0.15 10-29-04 ESO-6585 E-08 10.91 +/- 1.96 0.037 + 0.07 9.25 +/- 0.55 0.011 0.008 0.08 +/- 0.02 0.27 +/- 0.07 0.19 +/- 0.04 0.35 + 0.17 0.25 +/- 0.06 2.0 0.15 Collection Date Lab Code Location Gross Beta Be-7 K-40 Cs-1 37 TI-208 Pb-212 Bi-214 Ra-226 Ac-228 10-29-04 ESO-6586 E-09 27.72 +/- 2.69

-0.04 +/- 0.10 20.36 +/- 0.94 0.05 +/- 0.02 0.23 +/- 0.03 0.80 +/- 0.12 0.55 +/- 0.06 1.30 +/- 0.32 0.93 +/- 0.14 10-29-04 ESO-6587 E-20 26.05 +/- 2.67 0.41 +/- 0.14 15.79 +/- 1.04 0.09 +/- 0.04 0.17 +/- 0.04 0.54 +/- 0.04 0.45 +/- 0.07 0.92 +/- 0.31 0.69 +/- 0.19 2.0 0.15 31

POINT 3EACH NUCLEAR PLANT RADIOACTIVITY IN VEGETATION SAMPLES (Tr!-Annual Collections)

Sample Description and Concentration (pCVg wet)

Location Collection Date Lab Code Ratio (wet/dry)

Gross Beta Be-7 K-40 1-131 Cs-1 34 Cs-137 Other Gammasa E-01 05-26-04 EG-2564 4.06 5.52 t 0.11 E-02 05-26-04 EG-2565 5.52 4.91 +/-0.10 1.44 +/- 0.27 4.79

0.60 0.012 +/- 0.013

-0.006 +/- 0.016 0.004 +/- 0.013 0.017 +/- 0.014 E-03 05-26-04 EG-2566 5.21 6.28 +/- 0.12 0.71 +/- 0.30 5.59 +/- 0.63

-0.012 +/- 0.013

-0.004 +/- 0.014 0.005 +/- 0.014 0.001 +/- 0.013 Req. LLD 0.25 1.64 +/- 0.21 4.72 +/- 0.44

-0.002 +/- 0.008 0.003 +/- 0.008 0.000 +/- 0.008

-0.006 +/- 0.009 0.060 0.060 0.080 0.060 Location Collection Date Lab Code Ratio (wet/dry)

Gross Beta Be-7 K-40 1-131 Cs-1 34 Cs-1 37 Other Gammas" E-04 05-26-04 EG-2567 5.15 5.10 +/-0.10 0.91 +/- 0.23 5.57 +/- 0.67

-0.005 +/- 0.010 0.014 +/- 0.016 0.008 +/- 0.014 0.008 +/- 0.016 E-06 05-26-04 EG-2568 4.28 5.40 +/-0.11 1.08 +/- 0.32 6.09 +/- 0.66

-0.007 +/- 0.017 0.005 +/- 0.016 0.003 +/- 0.019

-0.016 +/- 0.017 E-08 05-26-04 EG-2569 Req. LLD 3.70 6.02 +/- 0.11 1.58 +/- 0.35 6.40 +/- 0.87 0.014 +/- 0.013 0.014 +/- 0.019 0.002 +/- 0.018 0.002 +/- 0.022 0.25 0.060 0.060 0.080 0.060 Location Collection Date Lab Code Ratio (wet/dry)

Gross Beta Be-7 K-40 1-131 Cs-1 34 Cs-1 37 Other Gammas' E-09 05-26-04 EG-2570 3.97 6.55 +/- 0.16 1.52 +/- 0.32 5.29 +/- 0.49 0.004 +/- 0.012

-0.006 +/- 0.011 0.010 +/- 0.012

-0.006 +/- 0.010 E-20 05-26-04 EG-2571 5.11 6.99 +/- 0.14 1.43 +/- 0.24 6.12 +/- 0.51

-0.015 +/- 0.009

-0.017 +/- 0.013 0.005 +/- 0.011 0.000 +/- 0.008 Req. LLD 0.25 0.060 0.060 0.080 0.060 8 See Introduction.

32

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN VEGETATION SAMPLES (Tri-Annual Collections)

Sample Description and Concentration (pCVg wet)

Location Collection Date Lab Code Ratio (wet/dry)

Gross Beta Be-7 K-40 1-131 Cs-1 34 Cs-1 37 Other Gammas" E-01 07-27-04 EG-4113 2.63 E-02 07-27-04 EG-4114 2.83 E-03 07-27-04 EG-4115 Req. LLD 2.34 6.04 +/- 0.17 0.88 5.51 0.001 0.005 0.000 0.003

+/- 0.28

+/- 0.67

+/- 0.013

+/- 0.016

+/- 0.014

+/- 0.016 6.34 +/- 0.17 1.10 +/- 0.32 5.05 +/- 0.65

-0.003 +/- 0.014 0.005 +/- 0.019

-0.004 +/- 0.016 0.001 +/- 0.013 7.66 +/- 0.20 0.96 +/- 0.24 8.37 +/- 0.89 0.009 +/- 0.014 0.001 +/- 0.016

-0.006 +/- 0.017

-0.003 +/- 0.017 0.25 0.060 0.060 0.080 0.060 Location Collection Date Lab Code Ratio (wet/dry)

Gross Beta Be-7 K-40 1-131 Cs-1 34 Cs-1 37 Other Gammas" E-04 07-27-04 EG-4116 2.54 5.42 +/-0.13 0.89 +/- 0.25 3.81 +/-0.46 0.001 +/- 0.011

-0.004 +/- 0.011 0.004 +/- 0.011 0.003 +/- 0.011

E-06

07-27-04 EG-4117 2.66 8.25 +/- 0.20 1.30 +/- 0.27 5.47 +/- 0.49

-0.022 +/- 0.008

-0.001 +/- 0.011 0.007 +/- 0.010 0.008 +/- 0.009 E-20 07-27-04 EG-4120 E-08 07-27-04 EG-4118 2.33 7.32 +/- 0.18 Req. LLD 0.25 0.96 4.90 0.015

-0.002 0.013

-0.001

+/- 0.29

+/- 0.51

+/-0.013

+/- 0.012

+/-0.013 0.060 0.060 0.080 0.060 Location Collection Date Lab Code Ratio (wet/dry)

Gross Beta Be-7 K-40 1-131 Cs-1 34 Cs-1 37 Other Gammas" E-09 07-27-04 EG-4119 2.78 Req. LLD 4.86 +/- 0.11 0.75 +/- 0.20 4.45 +/- 0.48 0.001 +/- 0.010 0.010 +/- 0.008 0.035 +/- 0.017

-0.003 +/- 0.009 2.85 5.60 +/- 0.13 1.03 +/- 0.32 6.21 +/- 0.74 0.013 +/- 0.016

-0.009 +/- 0.018 0.012 +/- 0.016 0.015 +/- 0.015 0.25 0.060 0.060 0.080 0.060 a See Introduction.

33

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN VEGETATION SAMPLES (Tri-Annual Collections)

Sample Description and Concentration (pCig wet)

Location Collection Date Lab Code Ratio (wet/dry)

Gross Beta Be-7 K-40 1-131 Cs-i34 Cs-1 37 Other Gammas" E-01 10-29-04 EG-6531 5.09 4.85 +/-t 0.20 1.72 +/- 0.23 3.70 +/- 0.33 0.005 +/-t 0.007 0.004 +/-t 0.008

-0.003 +/- 0.008 0.004 +/- 0.007 E-02 10-29-04 EG-6532 4.8 5.22 + 0.21 1.42 +/- 0.30 3.89 +/- 0.61

-0.006 +/- 0.008

-0.002 +/- 0.015

-0.006 +/- 0.013 0.008 +/- 0.016 E-03 10-29-04 EG-6533 4.52 4.03 +/- 0.15 2.48 +/- 0.34 4.02 +/- 0.46

-0.005 +/- 0.013 0.000 +/- 0.012 0.009 +/- 0.013

-0.001 +/- 0.012 Req. LLD 0.25 0.060 0.060 0.080 0.060 Location Collection Date Lab Code Ratio (wet/dry)

Gross Beta Be-7 K-40 1-131 Cs-1 34 Cs-137 Other Gammas' E-04 10-29-04 EG-6534 4.58 3.58 +/- 0.16 2.42 +/- 0.38 2.63 +/- 0.30 0.005 +/- 0.009 0.003 +/- 0.009

-0.004 +/- 0.010

-0.002 +/- 0.009 E-06 10-29-04 EG-6535 5.21 6.43 +/- 0.18 2.06 +/- 0.38 5.90 +/-h 0.72 0.003 +/- 0.012

-0.007 +/- 0.017 0.020 +/- 0.014 0.010 +/- 0.013 E-08 10-29-04 EG-6536 4.91 3.23 +/- 0.12 1.70 +/- 0.32 3.95 +/- 0.62

-0.007 +/- 0.014

-0.001 +/- 0.017 0.002 +/- 0.017 0.012 +/- 0.015 Req. LLD 0.25 0.060 0.060 0.080 0.060 Location Collection Date Lab Code Ratio (wet/dry)

Gross Beta E-09 10-29-04 EG-6537 4.07 5.33 +/- 0.19 E-20 10-29-04 EG-6538 Req. LLD 4.68 4.62 +/- 0.18 0.25 Be-7 K-40 1-131 Cs-1 34 Cs-1 37 Other Gammas" 2.23 3.99 0.020 0.002 0.008 0.009

+/- 0.24

+/- 0.35

+/- 0.009

+/- 0.008 2.13 +/- 0.26 3.58 +/- 0.44

-0.018 +/-t 0.009

-0.004 +/- 0.010 0.001 +/- 0.010 0.002 +/- 0.010 0.060 0.060 0.080 0.060 a See Introduction.

34

POINT BEACH NUCLEAR PLANT Aquatic Vegetation, analyses for gross beta and gamma emitting isotopes.

Collection: Semiannual Units: pCig wet Sample Description and Concentration Collection Date Lab Code Location Ratio (wet wtJdry wt.)

Gross Beta Be-7 K-40 Co-58 Co-60 Cs-1 34 Cs-I 37 Collection Date Lab Code Location Ratio (wet wt./dry wt.)

Gross Beta Be-7 K-40 Co-58 Co-60 Cs-1 34 Cs-1 37 Collection Date Lab Code Location Ratio (wet wtJdry wt.)

Gross Beta Be-7 K-40 Co-58 Co-60 Cs-1 34 Cs-137 06-05-04 ESL-2857 E-05 4.61 4.69 t 0.25 1.02 +/- 0.29 2.90 +/- 0.50 0.037 +/- 0.013 0.006 +0.013

-0.009 +/- 0.014 0.024 +/-0.016 08-04-04 ESL-4288 E-05 1.74 5.15 +/-0.91 0.42 +/-0.14 2.94 +/- 0.63 0.020 +/-0.017 0.027 +/- 0.024 0.007 +/-0.016 0.007 +/- 0.020 10-06-04 ESL-5741 E-05 4.25 4.82 +/- 0.38 0.39 +/-0.13 3.50 +/- 0.53 0.009 +/-0.010 0.005 +/- 0.015 0.001 +/-0.012 0.021 +/- 0.015 06-05-04 ESL-2858 E-1 2 3.37 2.13 +/- 0.26 0.87 +/- 0.30 1.23 +/- 0.42 0.007 +/- 0.015 0.008 +/- 0.013 0.008 + 0.022 0.021 +/- 0.021 08-04-04 ESL-4289 E-1 2 1.91 4.76 +/- 0.66 0.49 +/- 0.17 2.08 +/- 0.67 0.021 + 0.017

-0.014 +/- 0.025 0.008 +/- 0.017 0.023 +/- 0.023 10-06-04 ESL-5742 E-1 2 2.17 5.02 +/- 0.67 0.09 +/-0.11 3.10 +/- 0.54

-0.004 +/- 0.014 0.005 +/- 0.017

-0.009 +/- 0.014 0.009 +/- 0.015 Required LLD 0.25 0.25 0.25 0.25 0.25 Required LLD 0.25 0.25 0.25 0.25 0.25 Required LLD 0.25 0.25 0.25 0.25 0.25 35

POTNT RFACH4 Nl TCLFAR PLANT AMBIENT GAMMA RADIATION (TLD) 1 st. Quarter, 2004 Date Annealed:

12-15-03 Days in the field 86 Date Placed:

01-09-04 Days from Annealing Date Removed:

04-04-04 to Readout:

114 Date Read:

04-07-04 Days in Location Field Total mR Net mR Net mR per 7 days Indicator E-1 E-2 E-3 E-4 E-5 E-6 E-7 E-8 E-9 E-1 2 E-14 E-1 5 E-1 6 E-1 7 E-1 8 E-22 E-23 E-24 E-25 E-26 E-27 E-28 E-29 E-30 E-31 E-32 E-38 E-39 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 86 14.2 +/- 0.9 17.1 +/-0.8 17.8 i 1.2 15.3 i 1.3 17.1 +/-0.9 15.6 +/-0.9 15.6 +/- 0.8 15.3 +/- 0.8 17.9 +/- 0.3 13.6 +/- 0.4 16A +/- 0.5 17.0 +/- 0.4 16.4 +/- 0.4 16.9 +/- 0.5 17.0 +/- 0.8 16.7 +/- 1.1 15.9 +/- 0.4 16.3 +/- 0.6 15.1 +/-0.2 14.1 +/-0.2 15.4 +/- 0.2 13.5 +/- 0.4 14.7 +/- 0.7 15.2 +/- 0.6 17.2 +/- 0.6 15.9 +/- 0.5 16.5 +/- 1.3 14.7 +/- 0.5 9.5 +/- 1.2 12.4 +/- 1.1 13.1 +/-1.4 10.6 +/- 1.5 12.4 +/- 1.2 10.9 +/- 1.2 10.9 +/- 1.1 10.6 +/- 1.1 13.2 +/- 0.8 8.9 +/- 0.9 11.7 +/-0.9 12.3 +/- 0.9 11.7 +/- 0.9 12.2 +/- 0.9 12.3 +/- 1.1 12.0 +/- 1.3 11.2 +/- 0.9 11.6 +/- 1.0 10.4 +/-0.8 9.4 +/- 0.8 10.7 +/- 0.8 8.8 +/- 0.9 10.0 +/- 1.0 10.5 +/- 1.0 12.5 +/- 1.0 11.2 +/-0.9 11.8 +/- 1.5 10.0 +/- 0.9 0.77 +/- 0.10 1.01 +/- 0.09 1.06 +/- 0.12 0.86 +/- 0.12 1.01 +/- 0.10 0.89 +/- 0.10 0.89 +/- 0.09 0.86 +/- 0.09 1.07 +/- 0.07 0.72 +/- 0.07 0.95 +/- 0.07 1.00 +/- 0.07 0.95 +/- 0.07 0.99 +/- 0.07 1.00 +/- 0.09 0.97 +/- 0.11 0.91 +/- 0.07 0.94 +/- 0.08 0.84 +/- 0.06 0.76 +/- 0.06 0.87 +/- 0.06 0.71 +/- 0.07 0.81 +/- 0.08 0.85 +/- 0.08 1.02 +/- 0.08 0.91 +/- 0.07 0.96 +/- 0.12 0.81 +/- 0.07 Control E-20 86 15.7 +/- 0.8 11.0 +/- 1.1 0.89 +/- 0.09 Mean+/-s.d.

15.9.+/- 1.2 11.1 +/-1.2 0.91 +/- 0.09 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 12-15-03 01-30-04 Total mR 6.6 +/- 0.6 6.6 +/- 0.2 03-17-04 04-07-04 3.1 +/-0.3 2.6 +/- 0.3 36

PO(NT RHFACH-NU CT FAR PLANT AMBIENT GAMMA RADIATION (TLD) 2nd Quarter, 2004 Date Annealed:

03-17-04 Days in the field 88 Date Placed:

04-04-04 Days from Annealing Date Removed:

07-01-04 to Readout:

112 Date Read:

07-07-04 Days in Location Field Total mR Net mR Net mR per 7 days Indicator E-1 88 13.4 +/- 1.1 10.7 +/- 1.2 0.85 +/- 0.09 E-2 88 17.9 +/- 1.2 15.2 +/- 1.3 1.21 +/- 0.10 E-3 88 18.0 +/- 1.3 15.3 +/- 1.4 1.22 +/- 0.11 E-4 88 15.0 +/- 0.5 12.3 +/- 0.7 0.98 +/- 0.05 E-5 88 16.5 +/- 0.6 13.8 +/- 0.7 1.10 +/- 0.06 E-6 88 14.1 +/- 0.4 11.4 +/- 0.6 0.90 +/- 0.05 E-7 88 12.9 +/- 0.2 10.2 +/- 0.5 0.81 +/- 0.04 E-8 88 14.1 +/-0.6 11.4 +/- 0.7 0.90 +/-0.06 E-9 88 16.7+/-1.3 14.0+/-1.4 1.11 +/-0.11 E-12 88 11.6 +/-0.9 8.9 +/-1.0 0.71 +/-0.08 E-14 88 15.4 +/- 0.7 12.7 +/- 0.8 1.01 +/- 0.07 E-15 88 19.8 +/- 1.4 17.1 +/- 1.5 1.36 +/- 0.12 E-16 88 14.6 +/-0.3 11.9 +/-0.5 0.94 +/-0.04 E-17 88 15.0 +/- 0.8 12.3 +/- 0.9 0.98 +/- 0.07 E-18 88 16.0 +/- 0.4 13.3 +/- 0.6 1.06 +/- 0.05 E-22 88 16.2 +/- 0.2 13.5 +/- 0.5 1.07 +/- 0.04 E-23 88 16.7 +/-0.4 14.0 +/-0.6 1.11 +/-0.05 E-24 88 15.4 +/- 0.3 12.7 +/- 0.5 1.01 i0.04 E-25 88 16.1 +/- 0.3 13.4 +/- 0.5 1.06 0 0.04 E-26 88 13.0 +/- 0.3 10.3 +/- 0.5 0.82 +/- 0.04 E-27 88 15.1 +/- 0.5 12.4 +/- 0.7 0.98 i 0.05 E-28 88 12.3 +/- 0.3 9.6 +/- 0.5 0.76 i 0.04 E-29 88 13.4 +/- 0.6 10.7 +/- 0.7 0.85 +/- 0.06 E-30 88 14.8 +/- 0.3 12.1 +/- 0.5 0.96 +/- 0.04 E-31 88 17.0 +/-1.2 14.3 +/- 1.3 1.14 0.10 E-32 88 16.3 +/- 1.0 13.6 +/- 1.1 1.08 +/- 0.09 E-38 88 14.6 +/- 0.4 11.9 +/- 0.6 0.94 +/- 0.05 E-39 88 12.9 +/- 0.4 10.2 +/- 0.6 0.81 +/- 0.05 Control E-20 88 14.9 +/- 1.3 12.2 +/- 1.4 0.97 +/- 0.11 Mean+/-s.d.

15.2 +/- 1.9 12.4 +/- 1.9 0.99 +/- 0.14 In-Transit ExDosure Date Annealed 03-17-04 06-17-04 Date Read 04-07-04 07-07-04 Total mR ITC-1 3.1 +/- 0.3 2.6 +/- 0.1 ITC-2 2.6 +/- 0.3 2.6 +/- 0.1 37

POTNT 1FACH NIT TCLFAR PLANT AMBIENT GAMMA RADIATION (TLD) 3rd Quarter, 2004 Date Annealed:

06-17-04 Days in the field 98 Date Placed:

07-01-04 Days from Annealing Date Removed:

10-07-04 to Readout:

113 Date Read:

10-08-04 Days in Location Field Total mR Net mR Net mR per 7 days Indicator E-1 E-2 E-3 E-4 E-5 E-6 E-7 E-8 E-9 E-12 E-14 E-1 5 E-1 6 E-1 7 E-1 8 E-22 E-23 E-24 E-25 E-26 E-27 E-28 E-29 E-30 E-31 E-32 E-38 E-39 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 98 16.3 i 1.2 19.9 +/- 0.2 23.9 +/- 1.7 18.7 +/- 1.5 22.1 +/- 1.2 18.1 +/-1.2 19.8 +/- 0.8 18.2 +/- 0.8 22.3 +/- 0.6 14.7 +/- 0.4 20.9 +/- 0.6 23.3 +/- 0.7 20.3 +/- 0.3 21.8 +/- 0.9 22.6 +/- 1.0 21.3 +/- 1.5 21.5 +/- 0.7 20.4 +/- 0.5 19.5 +/- 0.2 17.1 +/-0.2 18.7 +/- 0.3 14.5 +/- 0.1 17.3 +/- 0.9 18.4 +/- 0.7 20.5 +/- 0.3 21.6 +/- 0.7 20.8 +/- 1.7 15.1 +/-0.5 13.6 +/- 1.2 17.2 +/- 0.4 21.2 +/- 1.7 16.0 +/- 1.5 19.4 +/- 1.2 15.4 +/- 1.2 17.1 +/-0.9 15.5 +/- 0.9 19.6 +/- 0.7 12.0 +/- 0.5 18.2 +/- 0.7 20.6 +/- 0.8 17.6 +/- 0.5 19.1 +/-1.0 19.9 +/- 1.1 18.6 +/- 1.5 18.8 +/- 0.8 17.7 +/- 0.6 16.8 +/- 0.4 14.4 +/- 0.4 16.0 +/- 0.5 11.8 +/- 0.4 14.6 +/- 1.0 15.7 +/-0.8 17.8 +/- 0.5 18.9 +/- 0.8 18.1 +/-1.7 12.4 +/- 0.6 0.97 +/- 0.09 1.23 +/- 0.03 1.51 +/- 0.12 1.14 +/- 0.11 1.39 +/- 0.09 1.10 +/- 0.09 1.22 +/- 0.06 1.11 +/- 0.06 1.40 +/- 0.05 0.86 +/- 0.04 1.30 +/- 0.05 1.47 +/- 0.06 1.26 +/- 0.03 1.36 +/- 0.07 1.42 +/- 0.08 1.33 +/- 0.11 1.34 +/- 0.06 1.26 +/- 0.04 1.20 +/- 0.03 1.03 +/- 0.03 1.14 +/- 0.03 0.84 +/- 0.03 1.04 +/- 0.07 1.12 +/- 0.06 1.27 +/- 0.03 1.35 +/- 0.06 1.29 +/- 0.12 0.89 +/- 0.04 Control E-20 98 19.1 +/-0.9 16.4 +/- 1.0 1.17 +/- 0.07 Mean+/-s.d.

19.6 +/- 2.5 16.9 +/- 2.5 1.21 +/- 0.18 Date Annealed Date Read ITC-1 ITC-2 In-Transit Exposure 06-17-04 09-20-04 07-07-04 10-08-04 Total mR 2.6 +/- 0.1 2.6 +/- 0.1 2.8 +/- 0.3 2.8 +/-0.1 38

POTNT BFACT4T M TCTFAR PLANT AMBIENT GAMMA RADIATION (TLD) 4th Quarter, 2004 Date Annealed:

09-20-04 Days in the field 89 Date Placed:

10-07-04 Days from Annealing Date Removed:

01-04-05 to Readout:

126 Date Read:

01-24-05 Days in Location Field Total mR Net mR Net mR per 7 days Indicator E-1 E-2 E-3 E-4 E-5 E-6 E-7 E-8 E-9 E-1 2 E-1 4 E-1 5 E-1 6 E-17 E-18 E-22 E-23 E-24 E-25 E-26 E-27 E-28 E-29 E-30 E-31 E-32 E-38 E-39 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 89 18.1 +/- 1.0 24.1 +/- 1.5 25.0 +/- 2.0 20.9 +/- 0.5 22.9 +/- 0.9 20.1 +/- 0.6 18.4 +/- 0.3 20.1 +/- 1.0 22.9 +/- 1.6 16.4 +/- 1.2 21.6 +/- 1.2 25.9 +/- 1.1 20.1 +/-0.5 20.8 +/- 1.3 21.8 +/- 0.2 21.8 +/- 0.6 22.9 +/- 0.7 21.0 +/- 0.5 22.1 +/- 0.3 18.4 +/- 0.3 20.6 +/- 0.7 15.9 +/- 0.3 19.0 +/- 0.8 20.5 +/- 0.3 23.3 +/- 1.7 22.1 +/- 1.4 19.9 +/- 0.6 15.5 +/- 0.5 13.6 +/- 1.2 19.6 +/- 1.7 20.5 +/- 2.1 16.4 +/- 0.9 18.4 +/- 1.1 15.6 +/- 0.9 13.9 +/- 0.8 15.6 +/- 1.2 18.4 +/- 1.7 11.9 +/- 1.4 17.1 +/-1.4 21.4 +/- 1.3 15.6 +/-0.9 16.3 +/- 1.5 17.3 +/- 0.7 17.3 +/- 0.9 18.4 +/- 1.0 16.5 +/- 0.9 17.6 +/- 0.8 13.9 +/- 0.8 16.1 +/- 1.0 11.4 +/- 0.8 14.5 +/- 1.1 16.0 +/- 0.8 18.8 +/- 1.8 17.6 +/- 1.6 15.4 +/-0.9 11.0 i0.9 1.07 +/- 0.10 1.54 +/- 0.13 1.61 +/- 0.17 1.29 +/- 0.07 1.45 +/- 0.09 1.23 +/- 0.07 1.09 +/- 0.06 1.23 +/- 0.10 1.45 +/- 0.14 0.94 +/- 0.11 1.34 +/- 0.11 1.68 +/- 0.10 1.23 +/- 0.07 1.28 +/- 0.12 1.36 +/- 0.06 1.36 +/- 0.07 1.45 +/- 0.08 1.30 +/- 0.07 1.38 +/- 0.06 1.09 +/- 0.06 1.27 +/- 0.08 0.90 +/- 0.06 1.14 +/- 0.08 1.26 +/- 0.06 1.48 +/- 0.14 1.38 +/- 0.12 1.21 +/- 0.07 0.87 +/- 0.07 Control E-20 89 19.6 +/- 1.3 15.1 +/- 1.5 1.19 +/- 0.12 Mean+/-s.d.

20.7 +/- 2.5 16.2 +/- 2.5 1.28 +/- 0.19 Date Annealed Date Read ITC-1 ITC-2 In-Transit Exposure 09-20-04 12-15-04 10-08-04 01-25-05 Total mR 2.8 +/- 0.3 6.4 +/- 0.6 2.8 +/- 0.1 6.0 +/- 0.2 39

N Environmental, bc.

Mdwest Laboratory an Allegheny Technologes Co.

7OoLa'de Road *Noittxook.?L 6OOe22 (47) S4407O0 to (47) 56444517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:

Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January through December, 2004

Appendix A Interlaboratorv Comparison ProQram Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Environmental Services Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.

Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

The results in Table A-2 list results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.

Table A-3 lists results of the analyses on in-house 'spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request. request.

Table A-5 list results of the in-house 'duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request.

The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program.

Attachment A lists acceptance criteria for "spiked" samples.

Out-of-limit results are explained directly below the result.

Al

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter

> 100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter

> 50 pCi/liter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCi/liter

> 30 pCi/liter or kg 10% of known value Potassium-40 2 0.1 g/liter or kg 5% of known value Gross alpha S 20 pCi/liter 5.0 pCi/liter

> 20 pCi/liter 25% of known value Gross beta s 100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium s 4,000 pCi/liter

+/-E la = (pCi/liter) 169.85 x (known)00933

> 4,000 pCi/liter 10% of known value Radium-226,-228 2 0.1 pCi/liter 15% of known value Plutonium 2 0.1 pCifliter, gram, or sample 10% of known value lodine-131, 5 55 pCi/liter 6.0 pCi/liter Iodine-129b

> 55 pCi/liter 10% of known value Uranium-238, s 35 pCi/liter 6.0 pCi/liter Nickel-63b

> 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/liter 10% of known value Othersb 20% of known value

' From EPA publication, Environmental Radioactivity Laboratory Intercomparison Studies Program. Fiscal Year, 1981-1982. EPA-60014-81-004.

b Laboratory limit.

A2

TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)".

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits STW-1005 STW-1005 STWV-1006 STW-1006 STW-1006 STW-1006 STW-1006 STW-1007 STW-1007 STW-1008 STW-1008 STW-1008 STW-1015 STW-1015 STW-1016 STW-1016 STW-1016 STW-1016 STW-1016 STW-1017 STW-1017 STW-1018 STW-1019 STW-1019 STW-1019 STW-1020 STW-1028 STW-1028 STW-1029 STW-1029 STW-1029 STW-1029 STW-1029 STW-1030 STW-1 030 STW-1030 STW-1 031 STW-1 031 STW-1031 02117/04 02/17/04 02/17/04 02/17/04 02/17/04 02/17/04 02/17/04 02/17/04 02/17/04 02/17/04 02/17/04 02/17/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 08/17/04 08/17/04 08/17/04 08/17/04 08/17/04 08117/04 08/17/04 08/17/04 08/17/04 08/17/04 08/17/04 08117/04 08/17/04 Sr-89 Sr-90 Ba-133 Co-60 Cs-I 34 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium Sr-89 Sr-90 Ba-1 33 Co-60 Cs-1 34 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 Sr-89 Sr-90 Ba-1 33 Co-60 Cs-1 34 Cs-137 Zn-65 Gr. Alpha Gr. Beta Gr. Beta Ra-226 Ra-228 Uranium 36.5 +/- 6.5 13.4 +/- 0.8 60.9 +/- 2.8 95.2 +/- 1.5 71.2 +/- 5.4 157.0 +/- 6.5 103.0 +/- 1.1 15.6 +/- 1.2 46.3 +/-4.4 8.7 +/-0.2 16.6 +/-0.4 34.2 +/-0.8 39.7 +/-3.3 12.4 +/-0.9 96.9 i 2.4 39.9 +/- 0.5 48.8 +/- 0.8 82.6 i 2.3 77.5 +/- 1.5 32.4 i 2.1 63.4 i 3.5 25.2 +/- 0.4

.16.0 +/- 1.1 12.6 +/- 0.9 13.0 +/- 0.0 32043 +/- 166 16.1 +/-1.9 13.4 +/- 0.1 30.2 +/- 3.9 24.9 +/- 1.9 21.4 +/- 3.4 205.6 +/- 4.3 145.5 +/- 3.0 47.7 +/- 9.1 28.1 +/-2.5 28.1 +/- 2.5 6.9 +/- 0.5 13.1 +/-1.4 6.0 +/- 0.1 44.9 +/- 4.5 11.6 +/- 1.2 63.2 +/- 6.3 96.4 +/- 9.6 75.8 +/- 7.6 155.0 +/- 15.5 102.0 +/- 10.2 16.6 +/- 1.7 41.5 +/-4.2 9.3 +/- 0.0 18.2 +/- 1.8 33.0 +/- 3.3 45.9 +/- 5.0 11.6 +/-5.0 101.0 +/- 10.1 41.6 +/-5.0 50.5 +/- 5.0 82.5 +/- 5.0 75.2 i7.5 38.8 i 9.7 59.6 +/- 10.0 25.1 +/- 3.0 17.3 +/-2.6 10.3 +/-2.6 12.7 +/-3.0 30900 +/-3090 20.0 +/- 2.0 13.6 +/- 1.4 32.1 +/-3.2 24.0 +/- 2.4 21.6 +/- 2.2 193.0 +/- 19.3 143.0 +/- 14.3 57.0 +/- 5.7 20.0 +/- 2.0 20.0 +/- 2.0 6.3 +/- 0.6 14.7 +/- 1.5 6.2 +/- 0.6 36.2 - 53.6 2.9 - 20.3 52.3 - 74.1 87.7 - 105.0 67.1 - 84.5 142.0 - 168.0 84.4 - 120.0 7.9 - 25.3 32.8 - 50.2 6.9 - 11.7 10.3 - 26.1 27.8 - 38.2 37.2 - 54.6 2.9 - 20.3 83.5 - 118.0 32.9 - 50.3 41.8 - 59.2 73.8 - 91.2 62.2 - 88.2 22.0 - 55.6 42.3 - 76.9 19.9 - 30.3 12.8 - 21.8 5.8 - 14.8 7.5 - 17.9 25600 - 36200 11.3 - 28.7 4.9 - 22.3 23.4 - 40.8 15.3 - 32.7 12.9 - 30.3 176.0 - 210.0 118.0 - 168.0 32.3 - 81.7 11.3 - 28.7 11.3 - 28.7 4.6 -7.9 8.3 - 21.1 1.0 - 11.4 Al-1

TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)".

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resulte Limits STW-1037 11/15/04 Sr-89 42.2 +/-3.5 45.7 + 5.0 37.0 -51.5 STW-1037 11/15/04 Sr-90 37.3 : 1.3 36.6 +/- 5.0 27.9 - 45.3 STW-1038 11/15/04 Ba-1 33 75.5 +/- 0.8 78.4 +/- 7.8 64.8 -92.0 STW-1038 11/15/04 Co-60 12.2 +/- 0.7 11.7 +/- 5.0 3.0 - 20.4 STW-1038 11/15104 Cs-134 43.6 +/-0.5 42.9 +/- 5.0 34.2 -51.6 STW-1038 11/15/04 Cs-137 59.5 +/-2.9 60.1 +/-5.0 51.4 -68.8 STW-1038 11/15/04 Zn-65 50.7 + 3.2 50.9 +/- 5.1 42.1 - 59.7 STW-1039 11/15/04 Gr. Alpha 23.9 +/-2.2 31.7 +/-7.9 18.0 -45.4 STW-1039 11/15/04 Gr. Beta 35.8 +/- 1.3 36.3 +/- 5.0 27.6 - 45.0 STW-1040 11/15/04 1-131 22.4 +/-1.9 22.0 +/-5.0 16.9 -27.3 STW-1041 11/15/04 Ra-226 9.8 +/-0.4 9.2 +/-1.4 6.8 -11.6 STW-1041 11/15/04 Ra-228 8.6 +/- 0.3 7.1 +/- 1.8 7.0 -10.2 STW-1041 11/15/04 Uranium 11.1 +/- 0.3 11.4 +/-3.0 6.2 -16.6 STW-1042 11/15/04 H-3 21218.0 +/- 285.0 20700.0 +/- 2070.0 17100.0 - 24300.0 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

Results are presented as the known values, expected laboratory precision (1 sigma,1 determination) and control limits as provided by ERA.

A1-2

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLDs).

mR Lab Code TLD Type Date Known Lab Result Control Description Value

+/- 2 sigma Limits Environmental. Inc.

2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 8/8/2003 8/8/2003 8/8/2003 8/8/2003 8/8/2003 8/8/2003 8/8/2003 8/8/2003 8/8/2003 Reader 1, 120 Reader 1, 150 Reader 1,180 Reader 1, 180 Reader 1,30 Reader 1. 60 Reader 1, 60 Reader 1.90 Reader 1,90 4.69 3.00 2.08 2.08 75.00 18.75 18.75 8.33 8.33 4.74 I 0.54 3.02 +/- 0.20 1.89 +/- 0.45 2.11 +/- 0.22 84.40 +/- 4.87 19.11 + 1.86 22.82 +/- 5.41 9.05 +/- 1.17 7.60 +/- 1.08 3.28 - 6.10 2.10 - 3.90 1.46 - 2.70 1.46 - 2.70 52.50 - 97.50 13.13 - 24.38 13.13 - 24.38 5.83 - 10.83 5.83 - 10.83 Environmental. Inc.

2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards 1/12/2004 1/12/2004 1/12/2004 1/12/2004 1/12/2004 1/12/2004 1/12/2004 1/12/2004 1/12/2004 Reader 1,30 Reader 1,60 Reader 1, 60 Reader 1, 90 Reader 1,90 Reader 1.120 Reader 1,150 Reader 1,150 Reader 1, 180 61.96 15.49 15.49 6.88 6.88 3.87 2.48 2.48 1.72 73.50 +/- 2.58 19.70 +/- 0.51 16.93 +/- 1.37 8.06 +/- 0.60 6.64 +/- 0.58 4.39 +/- 0.17 2.34 +/- 0.18 2.51 +/- 0.16 2.01 +/- 0.13 43.37 - 80.55 10.84 - 20.14 10.84 - 20.14 4.82 - 8.94 4.82 - 8.94 2.71 - 5.03 1.74 - 3.22 1.74 - 3.22 1.20 - 2.24 Environmental. Inc.

2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004 Reader 1, 30 cr Reader 1, 30 cr Reader 1, 60 cr Reader 1, 60 cr Reader 1, 90 cr Reader 1, 90 cr Reader 1, 120 c Reader 1, 150 c Reader 1, 180c 55.23 55.23 13.81 13.81 6.14 6.14 3.45 2.21 1.53 61.07 +/- 4.38 62.82 +/- 1.75 14.10 +/- 0.56 14.03 +/- 0.48 5.97 +/- 0.21 6.26 +/- 0.14 4.40 +/- 0.63 2.34 +/- 0.12 1.65 +/- 0.02 38.66 - 71.80 38.66 - 71.80 9.67 - 17.95 9.67 - 17.95 4.30 - 7.98 4.30 - 7.98 2.42 - 4.49 1.55 - 2.87 1.07 - 1.99 A2-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code Sample Date Analysis Laboratory results Known Control Type 2s. n=1b Activity Limitsc SPVE-707 SPCH-711 SPW-721 SPAP-733 SPW-735 SPW-735 SPW-735 SPW-735 SPMI-737 SPMI-737 SPMI-737 SPMI-737 SPW-1109 Vegetation Charcoal water Air Filter water water water water Milk Milk Milk Milk water 2/20/2004 1-131 (G) 2/20/2004 2/20/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 3/18/2004 1-131 (G)

Ni-63 Gr. Beta Cs-1 34 Cs-137 1-131 1-131 Cs-134 Cs-1 37 1-131 1-131 Fe-55 5.68 +/- 0.15 6.35 +/- 0.11 161.00 +/- 13.20 1.39 +/- 0.02 41.59 +/- 7.02 64.11 +/- 7.39 36.55 +/- 0.48 41.97 +/- 8.93 37.40 +/- 5.40 69.13 +/- 9.58 45.03 +/- 0.53 44.43 +/- 9.22 39.98 +/- 1.72 4.93 6.94 169.00 1.48 39.10 64.56 40.08 40.08 39.10 64.56 40.08 40.08 39.98 2.96 - 6.90

-3.06 - 16.94 101.40 - 236.60

-8.52 - 11.48 29.10 - 49.10 54.56 - 74.56 28.08 -52.08 28.08 - 52.08 29.10 - 49.10 54.56 - 74.56 28.08 - 52.08 28.08 - 52.08 23.99 - 55.97 SPW-1496 SPMI-1683 SPW-1683 SPW-1683 SPMI-1685 SPMI-1685 SPMI-1685 SPMI-1685 SPMI-1685 SPW-1686 SPW-1686 SPVE-1862 SPCH-1886 SPAP-1888 SPF-1917 SPF-1917 SPW-3151 SPW-4232 SPAP-4234 SPW-5712 SPW-5712 SPW-5712 SPMI-5714 water Milk water water Milk Milk Milk Milk Milk water water Vegetation Charcoal Air Filter Fish Fish water water Air Filter water water water Milk 4/7/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4116/2004 4/26/2004 4/26/2004 4/27/2004 4/29/2004 4/29/2004 6/24/2004 8/4/2004 814/2004 10/6/2004 10/612004 10/6/2004 10/6/2004 H-3 Sr-90 1-131 1-131 (G)

Cs-1 34 Cs-1 37 1-131 1-131(G)

Sr-90 Cs-1 34 Cs-137 1-131 (G) 1-131 (G)

Gr. Beta Cs-1 34 Cs-1 37 Fe-55 H-3 Gr. Beta Cs-134 Cs-137 Sr-90 Sr-90 80006.60 +/- 776.00 42.80 +/- 1.81 54.47 +/- 0.73 65.82 +/- 8.86 33.60 +/- 4.24 61.77 +/- 7.59 65.85 +/- 0.79 75.56 +/- 11.86 42.56 +/- 1.66 39.31 +/-4.35 67.73 +/- 7.92 1.32 +/- 0.03 2.90 +/- 0.07 1.35 +/- 0.02 1.44 +/- 0.04 1.33 +/- 0.06 33.85 +/- 1.61 80225.00 +/- 785.00 1.63 +/- 0.02 61.04 i 2.51 62.01 +/- 2.76 48.40 +/- 2.00 41.61 +/- 1.57 83896.00 43.43 66.60 66.60 37.29 64.36 66.60 66.60 43.43 37.29 64.36 1.12 2.80 1.48 1.47 1.29 37.32 82380.00 1.46 63.61 63.66 42.94 42.94 67116.80 - 100675.20 34.74 - 52.12 53.28 - 79.92 56.60 - 76.60 27.29 - 47.29 54.36 - 74.36 53.28 - 79.92 56.60 - 76.60 34.74 - 52.12 27.29 -47.29 54.36 - 74.36 0.67 - 1.57 1.68 - 3.92

-8.52 - 11.48 0.88 - 2.06 0.77 - 1.81 22.39 - 52.25 65904.00 - 98656.00

-8.54 - 11.46 53.61 - 73.61 53.66 - 73.66 34.35 - 51.53 34.35 - 51.53 A3-1

TABLE A-3. In-House "Spike' Samples Concentration (pCi/L)

Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=1b Activity Limits' SPMI-7418 Milk 12/22/2004 Cs-1 34 59.09 +/- 2.59 59.25 49.25 - 69.25 SPMI-7418 Milk 12/22/2004 Cs-137 65.45 +/- 5.61 63.35 53.35 - 73.35 SPW-7420 water 12/22/2004 Cs-134 58.42 +/- 1.99 59.25 49.25 - 69.25 SPW-7420 water 12/22/2004 Cs-1 37 64.26 +/- 4.18 63.35 53.35 -73.35 SPW-7420 water 12/22/2004 Sr-89 105.26 +/- 4.21 103.47 82.78 - 124.16 SPW-7420 water 12/22/2004 Sr-90 48.24 +/- 1.70 42.72 34.18 -51.26 SPAP-7437 Air Filter 12/22/2004 Gr. Beta 1.65 +/- 0.02 1.45

-8.55 - 11.45 SPF-7524 Fish 12/29/2004 Cs-134 1.11 +/- 0.03 1.27 0.76-1.78 SPF-7524 Fish 12/29/2004 Cs-137 1.21 +/-0.05 1.19 0.71 -1.67 SPW-7526 water 12/29/2004 H-3 78615.70 +/- 773.70 80543.00 64434.40 - 96651.60 SPW-7532 water 12/29/2004 Fe-55 30894.00 +/- 1484.00 32752.00 26201.60 - 39302.40 SPW-7540 water 12/29/2004 Tc-99 30.28 +/- 1.11 32.98 20.98 - 44.98 c Control limits are based on Attachment A, Page A2 of this report.

NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.

A3-2

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysis Laboratory results (4.66a)

Acceptance Type LLD Activity6 Criteria (4.66 a)

SPCH-712 SPW-722 SPAP-734 SPW-736 SPW-736 SPW-736 SPW-736 SPMI-738 SPMI-738 SPMI-738 SPMI-738 SPW-1110 SPW-1497 SPW-1684 SPW-1684 SPW-1684 SPW-1684 SPW-1684 SPW-1684 SPMI-1686 SPMI-1686 SPMI-1686 SPMI-1686 SPMI-1686 SPMI-1686c SPVE-1863 SPCH-1887 SPAP-1889 SPF-1918 SPF-1918 SPW-3152 SPW-4233 SPW-5711 SPW-5711 SPW-5711 SPW-5711 SPMI-5713 SPMI-5713 Charcoal water Air Filter water water water water Milk Milk Milk Milk water water water water water water water water Milk Milk Milk Milk Milk Milk Vegetation Charcoal Air Filter Fish Fish water water water water water water Milk Milk 2/20/2004 2/20/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 2/25/2004 3/18/2004 4/7/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/26/2004 4/26/2004 4/27/2004 4/29/2004 4/29/2004 6/24/2004 8/4/2004 10/6/2004 10/6/2004 10/6/2004 10/6/2004 10/6/2004 10/6/2004 1-131(G)

Ni-63 Gr. Beta Cs-1 34 Cs-1 37 1-131 1-131 (G)

Cs-134 Cs-1 37 1-131 1-131 (G)

Fe-55 H-3 Cs-134 Cs-137 1-131 1-131 (G)

Sr-89 Sr-90 Cs-134 Cs-137 1-131 1-131 (G)

Sr-89 Sr-90 1-131 (G) 1-131(G)

Gr. Beta Cs-134 Cs-137 Fe-55 H-3 Co-60 Cs-134 Cs-1 37 Sr-90 Cs-1 34 Cs-1 37 0.01 131.80 0.00 2.47 1.91 0.15 3.24 2.54 5.34 0.16 5.36 0.77 152.30 2.43 2.53 0.50 4.49 0.64 5.00 4.16 0.45 6.53 0.71 0.71 0.00 0.02 0.00 0.01 0.01 0.79 154.23 4.26 6.02 5.28 0.61 4.60 5.81

-39.8 +/- 79.000

-0.003 +/- 0.001

-0.031 +/- 0.100

-0.071 +/-0.104 0.17 +/- 0.480 81.4 +/- 79.400 0.21 i0.260 0.19 i0.520 0.13 +/- 0.310 0.13 i 0.240 0.11 +/-0.700 0.66 i 0.400

-0.003 i 0.001

-0.07 +/- 0.470 102.67 +/- 81.380

-0.13 +/- 0.270 9.6 20 3.2 10 10 0.5' 20 10 10 0.5 20 1000 200 10 10 0.5 20 5

1 10 10 0.5 20 5

1 20 9.6 3.2 100 100 1000 200 10

'10 10 I

10 10 A4-1

TABLE A-4. In-House Blank' Samples Concentration (pCi/L)3 Lab Code Sample Date Analysis Laboratory results (4.66a)

Acceptance Type LLD Activityb Criteria (4.66 c)

SPMI-7419 SPMI-7419 SPMI-7419c SPW-7421 SPW-7421 SPAP-7438 SPF-7525 SPF-7525 SPW-7526 SPW-7533 SPW-7540 Milk Milk Milk water water Air Filter Fish Fish water water water 12/22/2004 12/22/2004 12/22/2004 12/22/2004 12/22/2004 12/22/2004 12/29/2004 12/29/2004 12/29/2004 12/29/2004 12/29/2004 Cs-1 34 Cs-1 37 Sr-90 Sr-89 Sr-90 Gr. Beta Cs-1 34 Cs-137 H-3 Fe-55 Tc-99 8.66 5.61 0.82 1.21 0.82 0.00 0.01 0.01 164.80 753.00 1.19 1.67 + 0.480 0.58 +/- 0.940 0.26 +/- 0.410

-0.0002 +/- 0.001

-47 +/- 84.600 118.6 +/- 465.800

-0.036 +/- 0.720 10 10 I

5 1

3.2 100 100 200 1000 10

' Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

b The activity reported is the net activity result.

' Low levels of Sr-90 are still detected In the environment. A cancentration of (1-5 pCQL) in milk is not unusual.

A4-2

TABLE A-5. In-House 'Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date E-30, 31 E-30, 31 WW-58, 59 WW-58. 59 TD-7889, 7890 MI-79, 80 MI-79, 80 S-100. 101 SW-225, 226 SW-225, 226 U-304, 305 SW-345, 346 SWT-423, 424 SWU-469. 470 TD-545, 546 MI-524. 525 MI-567, 568 MI-567. 568 MI-588, 589 SWU-778, 779 LW-1014, 1015 SW-966, 967 SW-966, 967 SW-966, 967 SW-1249, 1250 LW-1464, 1465 AP-1633.1634 AP-1714, 1715 TD-1489. 1490 SWT-1299, 1300 DW-1420. 1421 DW-1510. 1511 BS-1537. 1538 WW-1654, 1655 LW-1680, 1681 MI-1735,1736 MI-1802,1803 MI-1802,1803 U-1781, 1782 SWT-1933, 1934 F-1912, 1913 F-1912, 1913 LW-1960, 1961 1/5/2004 1/5/2004 1/512004 1/5/2004 1/5/2004 1/712004 1/7/2004 1/13/2004 1/13/2004 1/13/2004 1/16/2004 1/27/2004 1/27/2004 1/27/2004 2/2/2004 2/4/2004 2/9/2004 2/9/2004 2/11/2004 2/2412004 3/1/2004 3/9/2004 3/9/2004 3/9/2004 3/31/2004 3/31/2004 3/31/2004 3/31/2004 411/2004 4/2/2004 4/2/2004 4/2/2004 4/6/2004 4/13/2004 4/1312004 4/14/2004 4/19/2004 4/19/2004 4/21/2004 4127/2004 4/29/2004 4/2912004 4/29/2004 Analysis Gr. Beta K-40 Gr. Beta K40 H-3 K-40 Sr-90 Cs-137 Gr. Alpha Gr. Beta Gr. Beta 1-131 Gr. Beta Gr. Beta H-3 K-40 K-40 Sr-90 K-40 Gr. Beta Gr. Beta Gr. Alpha Gr. Beta H-3 Gr. Beta Gr. Beta Be-7 Be-7 H-3 Gr. Beta Gr. Beta 1-131 Gr. Beta Gr. Beta Gr. Beta K-40 K-40 Sr-90 Gr. Alpha Gr. Beta H-3 K-40 Gr. Beta First Result Second Result Result 1.27 +/- 0.06 1.33 +/- 0.21 4.20 +/- 1.33 2.30 +/- 0.23 16582.00 +/- 366.00 1451.50 +/- 125.90 0.90 +/- 0.31 8.50 +/- 0.23 2.62 +/- 1.26 6.37 +/- 1.15 5.18 +/- 1.38 1.32 +/- 0.24 2.34 +/- 0.54 2.99 +/- 0.57 658.40 +/- 104.60 1240.00 +/- 147.90 1322.90 +/- 105.50 0.98 +/- 0.48 1185.70 +/- 157.80 2.55 +/- 0.54 1.78 +/- 0.56 2.70 +/- 1.43 8.06 +/- 1.20 182.04 +/- 86.24 4.71 +/-1.11 2.13 + 0.52 0.05 +/- 0.02 0.04 + 0.01 681.00 + 110.00 3.13 + 0.57 1.29 +/- 0.83 0.68 +/- 0.27 6.81 +/- 1.20 6.83 +/- 1.17 2.45 + 0.64 1384.90 +/- 182.00 1327.50 +/- 109.10 0.72 +/- 0.40 0.20 +/- 1.90 2.60 +/- 0.55 8875.00 +/- 250.00 3406.90 +/- 533.30 2.23 +/- 0.55 1.26 +/- 0.05 1.11 +/- 0.20 4.46 +/- 1.34 2.70 +/- 0.27 16060.00 +/- 360.00 1383.60 +/- 115.50 1.05 +/- 0.34 8.52 +/- 0.21 2.05 +/- 1.16 4.92 +/- 1.06 7.04 +/- 1.53 1.56 +/- 0.21 2.38 +/- 0.52 3.09 +/- 0.67 712.30 +/- 106.60 1265.60 +/- 166.30 1340.80 +/- 112.80 0.79 +/- 0.42 1337.70 +/- 160.00 2.53 +/- 0.56 2.06 +/- 0.57 2.96 +/- 1.63 7.33 +/- 1.21 198.87 +/- 86.97 5.25 _ 1.10 2.39 0.53 0.05 0.02 0.05 +/- 0.01 709.00 i 111.00 3.64 +/- 0.60 1.62 +/- 0.87 0.62 +/- 0.36 6.76 +/- 1.23 5.60 +/- 1.12 2.93 +/- 0.62 1408.20 +/- 187.90 1206.30 +/- 113.30 0.77 +/- 0.41

-0.30 +/- 2.40 2.33 +/- 0.52 9119.00 +/- 253.00 3550.60 +/- 581.40 2.38 +/- 0.57 1.27 +/- 0.04 1.22 +/- 0.15 4.33 +/- 0.94 2.50 +/- 0.18 16321.00 +/- 256.69 1417.55 85.43 0.97 0.23 8.51 _ 0.16 2.34 +/- 0.86 5.65 i 0.78 6.11 1.03 1.44 _ 0.16 2.36 _ 0.38 3.04 + 0.44 685.35 _ 74.67 1252.80 +/- 111.28 1331.85 +/- 77.22 0.89 +/- 0.32 1261.70 +/- 112.36 2.54 +/- 0.39 1.92 +/- 0.40 2.83 +/- 1.08 7.69 +/- 0.85 190.45 +/- 61.24 4.98 +/- 0.78 2.26 +/- 0.37 0.05 +/- 0.01 0.05 +/- 0.01 695.00 +/- 78.14 3.39 _ 0.41 1.46 i 0.60 0.65 +/- 0.23 6.78 +/- 0.86 6.21 _ 0.81 2.69 +/- 0.45 1396.55 _ 130.80 1266.90 +/- 78.64 0.74 +/- 0.28

-0.05 +/- 1.53 2.46 0.38 8997.00 + 177.84 3478.75 _ 394.47 2.31 _ 0.40 A5-1

TABLE A-5. In-House 'Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result I

BS-2083. 2084 BS-2083, 2084 BS-2083, 2084 BS-2083. 2084 MI-2225. 2226 SW-2267, 2268 SW-2267, 2268 Mi1-2437, 2438 MI-2437, 2438 F-2413, 2414 SO-2578, 2579 SO-2578. 2579 SO-2578. 2579 SS-2603. 2604 SS-2603. 2604 G-2677, 2678 G-2677. 2678 G-2677, 2678 G-2677, 2678 DW-2700, 2701 TD-2876, 2877 MI-2724. 2725 MI-2724. 2725 BS-2921, 2922 TD-2876, 2877 BS-2897. 2898 SWU-3092, 3093 CF-2986. 2987 CF-2986, 2987 MI-2977, 2978 MI-3007, 3008 W-3031, 3032 W-3071, 3072 SW-3145, 3146 DW-3278, 3279C AP-3922. 3923 AP-3637, 3638 LW-3589, 3590 LW-3589, 3590 LW-3589, 3590 AP-3943, 3944 5/3/2004 5/3/2004 5/3/2004 5/3/2004 5/11/2004 5/11/2004 5/11/2004 5/17/2004 5/1712004 5/20/2004 5/2612004 5/26/2004 5/26/2004 5/26/2004 5/26/2004 6/1/2004 6/11/2004 611/2004 6/1/2004 6/1/2004 6/1/2004 6/3/2004 6/312004 6/3/2004 6/4/2004 6/4/2004 6/9/2004 6/14/2004 6/14/2004 6/15/2004 6/15/2004 6118/2004 6/21/2004 6/22/2004 6/25/2004 6/28/2004 6/29/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 Be-7 Gr. Beta K-40 Sr-90 K-40 Gr. Alpha Gr. Beta K-40 Sr-90 K-40 Cs-137 Gr. Beta K-40 Cs-1 37 K-40 Be-7 Gr. Beta K-40 Sr-90 Gr. Beta H-3 K-40 Sr-90 K-40 H-3 Gr. Beta Gr. Beta Be-7 K-40 K-40 K-40 H-3 H-3 1-131 1-131 Be-7 Be-7 Gr. Alpha Gr. Beta H-3 Be-7 1.10 +/- 0.44 28.44 +/- 2.27 6.75 +/- 0.89 0.12 +/- 0.04 1396.30 +/- 124.20 2.95 +/- 1.44 6.80 +/- 1.18 1549.00 +/- 123.40 1.83 +/- 0.44 2844.60 +/- 550.40 0.16 +/- 0.02 28.07 +/- 3.24 19.41 +/- 0.78 0.06 +/- 0.02 10.1.8 +/- 0.63 1.31 +/- 0.25 5.73 +/- 0.12 5.56 +/- 0.49 0.01 +/- 0.00 1.82 +/- 1.01 13116.00 +/- 324.00 1509.00 +/- 116.10 1.64 +/- 0.46 8.32 +/- 0.63 13116.00 +/- 324.00 9.31 i 1.43 1.95 +/- 0.71 0.69 i 0.12 4.50 i 0.32 1486.70 +/- 120.10 1333.90 i 121.30 642.00 i 108.00 273.00 +/- 94.00 0.97 +/- 0.20 0.67 +/- 0.26 0.08 +/- 0.01 0.08 +/- 0.01 0.28 i 0.55 1.91 i0.64 8369.20 i 262.57 0.08 i 0.02 1.17 +/- 0.20 25.56 +/- 2.04 6.35 +/- 0.53 0.17 +/- 0.05 1227.60 +/- 125.40 2.41 +/- 1.37 7.25 +/- 1.21 1566.20 +/- 118.60 1.99 +/- 0.42 2963.00 +/- 532.30 0.21 +/- 0.05 28.73 +/- 3.00 18.93 +/- 1.04 0.06 +/- 0.02 10.43 +/- 0.56 1.25 +/- 0.23 5.86 +/- 0.12 5.78 +/- 0.50 0.01 +/- 0.01 2.66 +/- 0.94 12746.00 +/- 320.00 1489.20 +/- 126.10 1.81 +/- 0.44 8.55 +/- 0.62 12746.00 +/- 320.00 8.82 +/- 1.39 2.55 +/- 0.76 0.84 +/- 0.19 3.82 +/- 0.48 1291.60 +/- 167.40 1355.80 +/- 176.50 562.00 +/- 105.00 203.00 +/- 92.00 1.43 +/- 0.20 0.48 +/- 0.25 0.07 +/- 0.01 0.07 +/- 0.01 1.29 +/- 0.89 2.86 +/- 0.70 8226.01 +/- 260.51 0.09 +/- 0.02 1.14 +/- 0.24 27.00 +/- 1.53 6.55 +/- 0.52 0.15 +/- 0.03 1311.95 +/- 88.25 2.68 +/- 0.99 7.03 +/- 0.84 1557.60 +/- 85.58 1.91 +/- 0.30 2903.80 +/- 382.85 0.18 +/- 0.03 28.40 +/- 2.21 19.17 +/- 0.65 0.06 +/- 0.02 10.30 +/- 0.42 1.28 +/- 0.17 5.79 +/- 0.09 5.67 +/- 0.35 0.01 +/- 0.00 2.24 +/- 0.69 12931.00 +/- 227.69 1499.10 +/- 85.70 1.73 +/- 0.32 8.44 +/- 0.44 12931.00 +/- 227.69 9.06 +/- 1.00 2.25 +/- 0.52 0.76 +/- 0.11 4.16 +/- 0.29 1389.15 +/- 103.01 1344.85 +/- 107.08 602.00 +/- 75.31 238.00 +/- 65.76 1.20 +/- 0.14 0.57 +/- 0.18 0.07 +/- 0.01 0.07 +/- 0.01 0.79 +/- 0.53 2.39 +/- 0.48 8297.61 +/- 184.94 0.08 +/- 0.01 A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Sdcond Result Result E-3377, 3378 E-3377, 3378 G-3377. 3378 G-3377, 3378 G-3377, 3378 VE-3681. 3682 CF-3707, 3708 CF-3707, 3708 SW-3773, 3774 LW-3849, 3850 SWU-4307, 4308 Ml-4051. 4052 VE-4079, 4080 MI-4163, 4164 Ml-4163, 4164 WW-4387, 4388 MI-4286,4287 Ml-4286,4287 VE-4370, 4371 VE-4408, 4409 VE-4467, 4468 MI-4492,4493 MI-4492, 4493 MI-4518,4519 VE-4748, 4749 VE-4748, 4749 LW-4769, 4770 ME-4905. 4906 ME-4905,4906 MI-4926, 4927 MI-4926, 4927 VE-5027, 5028 VE-5027, 5028 SW-5003, 5004 MI-5050, 5051 MI-5050, 5051 WW-5072, 5073 SW-5216. 5217 SW-5216, 5217 7/1/2004 7/1/2004 7/1/2004 7/1/2004 7/1/2004 7/13/2004 7/13/2004 7/13/2004 7/14/2004 7/14/2004 7/14/2004 7/28/2004 7/28/2004 7/28/2004 7/28/2004 8/3/2004 8/4/2004 8/4/2004 8/4/2004 8/5/2004 8/9/2004 8/10/2004 8/10/2004 8/11/2004 8/25/2004 8/25/2004 8/26/2004 9/1/2004 9/1/2004 9/1/2004 9/1/2004 9/2/2004 9/2/2004 9/7/2004 9!7/2004 917/2004 9/7/2004 9/14/2004 9/14/2004 Gr. Beta K-40 Be-7 Gr. Beta K-40 K-40 Be-7 K-40 H-3 Gr. Beta Gr. Beta K-40 K-40 K-40 Sr-90 Gr. Beta K-40 Sr-90 H-3 K-40 K-40 K-40 Sr-90 K-40 Gr. Beta K-40 Gr. Beta Gr. Beta K-40 K-40 Sr-90 Gr. Beta K-40 1-131 K-40 Sr-90 Gr. Beta Gr. Alpha Gr. Beta 1.21 +/- 0.06 1.08 + 0.20 1.10 +/- 0.13 6.42 +/- 0.19 5.26 +/- 0.31 2.65 +/- 0.45 1.97 +/- 0.44 5.39 +/- 0.44 10697.20 +/- 295.70 2.21 +/- 0.54 3.49 +/- 0.57 1190.70 +/- 204.60 4.90 +/- 0.51 1422.40 +/- 186.50 0.87 +/- 0.32 5.94 +/- 0.76 1435.20 +/- 76.90 1.88 +/- 0.40 0.54 +/- 0.08 2.03 +/- 0.39 6.28 +/- 0.76 1478.70 +/- 116.70 1.35 +/- 0.40 1197.30 +/- 158.50 2.31 +/- 0.05 1.70 +/- 0.25 2.00 +/- 0.58 3.06 +/- 0.10 2.33 +/- 0.67 1316.20 +/- 115.40 3.62 +/- 0.52 2.43 +/- 0.07 1.77 +/- 0.20 1.69 +/- 0.23 1559.40 +/- 131.80 2.26 +/- 0.52 4.31 +/- 0.70 4.34 +/- 1.71 7.97 +/- 1.24 1.35 +/- 0.07 1.30 +/- 0.22 1.16 + 0.16 6.28 +/- 0.19 5.36 +/- 0.28 2.90 +/- 0.61 2.11 +/- 0.25 4.98 +/- 0.42 10689.60 +/- 295.70 2.32 +/- 0.65 3.68 +/- 0.61 1357.00 +/- 145.90 4.62 +/- 0.61 1330.80 +/- 181.00 1.00 + 0.35 6.28 + 0.76 1404.70 +/- 80.54 1.31 +/- 0.35 0.62 +/- 0.08 2.12 + 0.32 6.11 +/- 0.75 1472.50 +/- 105.10 1.08 +/- 0.42 1350.20 +/- 202.30 2.32 +/- 0.05 1.94 +/- 0.31 2.07 +/- 0.58 2.93 +/- 0.10 3.26 +/- 0.58 1285.80 +/- 117.30 2.07 +/- 0.43 2.39 +/- 0.06 1.94 +/- 0.31 1.50 +/- 0.25 1560.70 +/- 121.20 1.61 +/- 0.47 4.11 +/-0.69 4.30 +/- 1.77 8.58 + 1.29 1.28 +/- 0.05 1.19 +/- 0.15 1.13 +/- 0.10 6.35 +/- 0.13 5.31 +/- 0.21 2.77 +/- 0.38 2.04 +/- 0.25 5.19 +/- 0.30 10693.40 +/- 209.09 2.27 +/- 0.42 3.59 +/- 0.42 1273.85 +/- 125.65 4.76 +/- 0.40 1376.60 +/- 129.95 0.93 +/- 0.24 6.11 +/- 0.54 1419.95 +/- 55.68 1.59 +/- 0.26 0.58 +/- 0.06 2.08 +/- 0.25 6.20 +/- 0.53 1475.60 +/- 78.53 1.22 +/- 0.29 1273.75 +/- 128.50 2.31 +/- 0.04 1.82 +/- 0.20 2.04 +/- 0.41 3.00 +/- 0.07 2.80 +/- 0.44 1301.00 +/- 82.27 2.84 +/- 0.34 2.41 +/- 0.05 1.86 +/- 0.18 1.59 +/- 0.17 1560.05 +/- 89.53 1.94 +/- 0.35 4.21 +/- 0.49 4.32 +/- 1.23 8.27 +/- 0.89 A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCiIL)a Averaged Lab Code Date Analysis First Result Second Result Result G-5237, 5238 G-5237, 5238 LW-5316, 5317 SS-5450, 5451 AP-6308, 6309 SWU-5495. 5496 AP-6070, 6071 G-5516, 5517 G-5516, 5517 AP-6258, 6259 F-7211, 7212 F-7211, 7212 BS-5902, 5903 BS-5902, 5903 E-5654, 5655 E-5654. 5655 MI-5676, 5677 SO-5756. 5757 SO-5756, 5757 SO-5756. 5757 VE-6483, 6484 MI-5923, 5924 SS-6046, 6047 SS-6046, 6047 SS-6046, 6047 DW-6208, 6209 BS-6694, 6695 VE-6354, 6355 VE-6354, 6355 DW-6462, 6463 LW-6377, 6378 SS-6504. 6505 LW-6762, 6763 BS-6576, 6577 BS-6576, 6577 SO-6715, 6716 SO-6715, 6716 SO-6715. 6716 SO-6715, 6716 VE-6673. 6674 VE-6673, 6674 VE-6673, 6674 9/15/2004 9/15/2004 9/16/2004 9/24/2004 9/27/2004 9/2812004 9/28/2004 9/29/2004 9/29/2004 9/2912004 9/29/2004 9/29/2004 10/1/2004 10/1/2004 10/4/2004 10/4/2004 10/4/2004 1014/2004 1014/2004 10/4/2004 10/612004 10112/2004 1011312004 10113/2004 10113/2004 10115/2004 10119/2004 10/25/2004 10/2512004 10/27/2004 10128/2004 10129/2004 10/31/2004 11/1/2004 11/1/2004 11/2/2004 11/2/2004 1112/2004 11/212004 11/812004 11/5/2004 11/8/2004 Be-7 K-40 Gr. Beta K-40 Be-7 Gr. Beta Be-7 Be-7 K-40 Be-7 Cs-137 K-40 Co-60 Co-60 Gr. Beta K-40 K-40 Gr. Alpha Gr. Beta K-40 K-40 K-40 Cs-137 Gr. Beta K-40 1-131 K-40 Gr. Beta K-40 Gr. Beta Gr. Beta K-40 Gr. Beta Gr. Beta K-40 Cs-137 Gr. Alpha Gr. Beta K-40 Gr. Alpha Gr. Beta K-40 1.18 +/- 0.23 7.16 +/- 0.58 2.76 i 0.58 10.33 i 0.66 0.08 i 0.01 3.38 i 1.78 0.08 i 0.01 1.81 i 0.29 7.35 i 0.70 0.07 i 0.01 0.04 i 0.01 2.76 i 0.27 0.25 i 0.05 2.53 i 0.11 1.40 i 0.06 1.32 i 0.26 1311.00 i 122.00 7.12 i 3.09 19.66 i 2.63 16.45 i 0.86 9.35 +/- 0.55 1333.60 +/- 183.50 0.02 +/- 0.01 7.93 +/- 1.72 5.77 +/- 0.42 0.89 +/- 0.26 11.84 +/- 0.67 4.82 +/- 0.14 4.71 +/- 0.54 8.46 +/- 1.27 2.18 +/- 0.54 9.28 +/- 0.61 1.85 +/- 0.66

-11.02 +/- 1.54 9.43 +/- 0.71 0.29 +/- 0.04 10.94 +/- 3.95 21.33 +/- 3.10 10.42 +/- 0.71 0.07 +/- 0.04 4.50 +/- 0.12 4.05 +/- 0.49 1.28 +/- 0.24 7.56 +/- 0.55 2.64 +/- 0.54 10.10 +/- 0.74 0.08 +/- 0.01 4.41 +/- 1.94 0.08 +/- 0.01 1.74 +/- 0.30 7.43 +/- 0.62 0.07 +/- 0.01 0.05 +/- 0.02 3.07 +/- 0.26 0.26 +/- 0.03 2.52 +/- 0.06 1.32 +/- 0.06 1.22 +/- 0.24 1398.00 +/- 125.00 6.69 +/- 2.92 22.32 +/- 2.65 17.52 +/- 0.78 9.88 +/- 0.23 1552.40 +/- 179.20 0.02 +/- 0.01 9.57 +/- 1.88 5.77 +/- 0.40 0.65 +/- 0.27 12.75 +/- 0.79 4.76 +/- 0.14 4.82 +/- 0.61 8.22 +/- 1.24 2.33 +/- 0.53 8.51 +/- 0.78 1.69 +/- 0.64 13.77 +/- 1.77 8.84 +/- 0.68 0.33 +/- 0.06 14.72 +/- 4.16 24.82 +/- 3.10 12.16 +/- 1.06 0.14 +/- 0.05 4.48 +/- 0.12 4.65 +/- 0.55 1.23 +/- 0.17 7.36 +/- 0.40 2.70 +/- 0.40 10.22 +/- 0.50 0.08 +/- 0.01 3.90 +/- 1.32 0.08 +/- 0.01 1.77 +/- 0.21 7.39 +/- 0.47 0.07 +/- 0.01 0.05 +/- 0.01 2.92 +/- 0.19 0.25 +/- 0.03 2.52 +/- 0.06 1.36 +/- 0.04 1.27 +/- 0.18 1354.50 +/- 87.33 6.91 +/- 2.13 20.99 i 1.87 16.99 i 0.58 9.61 i 0.30 1443.00 +/- 128.24 0.02 i 0.01 8.75 +/- 1.27 5.77 +/- 0.29 0.77 i 0.19 12.29 i 0.52 4.79 +/- 0.10 4.77 i 0.41 8.34 i 0.89 2.25 +/- 0.38 8.89 +/- 0.50 1.77 +/- 0.46 12.40 +/- 1.17 9.14 +/- 0.49 0.31 +/- 0.04 12.83 +/- 2.87 23.07 +/- 2.19 11.29 i 0.64 0.11 +/- 0.03 4.49 +/- 0.09 4.35 +/- 0.37 A5-4

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)8 Averaged Lab Code Date Analysis First Result Second Result Result SO-6820, 6821 11/10/2004 K-40 14.41 +/- 1.03 15.01 +/- 1.09 14.71 +/- 0.75 SO-6820, 6821 11/10/2004 Sr-90 0.04 +/- 0.02 0.07 +/- 0.02.

0.06 +/- 0.02 SWU-7160, 7161 11/30/2004 Gr. Beta 4.39 +/- 1.98 3.09 +/- 1.77 3.74 +/- 1.33 MI-7062, 7063 12/112004 K-40 1456.00 +/- 124.80 1640.50 +/- 131.40 1548.25 +/- 90.61 MI-7062, 7063 12/1/2004 Sr-90 1.13 +/- 0.41 0.98 +/- 0.43 1.06 +/- 0.30 S-7281. 7282 12/5/2004 Cs-137 0.82 +/- 0.15 1.16 +/-0.20 0.99 +/- 0.12 VE-7343, 7344 12/13/2004 Gr. Beta 5.25 +/- 0.14 5.08 +/- 0.14 5.16 +/- 0.10 VE-7343. 7344 12/13/2004 K-40 4.23 +/- 0.71 4.33 +/- 0.69 4.28 +/- 0.49 MI-7317. 7318 12/14/2004 K-40 1702.80 +/- 129.70 1536.80 +/- 115.10 1619.80 +/- 86.70 WW-7375, 7376 12/14/2004 Gr. Beta 14.13 +/- 1.03 15.22 +/- 1.06 14.68 +/- 0.74 SWU-7507,7508 12/14/2004 Gr. Beta 4.48 +/- 0.66 5.31 +/- 0.69 4.89 +/- 0.48 DW-7563. 7564 12/27/2004 Gr. Beta 1.88 +/- 0.51 2.34 +/- 0.52 2.11 +/- 0.37 P-7698. 7699 12/27/2004 H-3 246.01 +/- 95.00 259.06 +/- 95.51 252.53 +/- 67.35 AP-7741. 7742 12/28/2004 Be-7 0.06 +/- 0.02 0.05 +/- 0.02 0.05 +/- 0.01 Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

a Results are reported in units of pCiIL, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).

b 600 minute count time or longer, resulting in lower error.

A5-5

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity Limits' STSO-1 022 soil STSO-1022. soil STSO-1022 soil STSO-1022 soil STSO-1022 soil STSO-1022 soil STSO-1 022 soil STSO-1 022 "" soil STSO-1022 a'soil STSO-1022 '" soil STSO-1022 soil 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 K-40 Ni-63 Tc-99 U-23314 U-238 Zn-65 65.90 +/- 4.50 388.90 +/- 4.00 524.80 +/- 7.10 403.40 +/- 4.60 829.10 +/- 7.60 620.60 +/- 29.50 254.80 +/- 8.40 59.00 +/- 6.00 24.70 +/- 3.60 24.20 +/- 3.50 743.00 +/- 13.10 66.97 +/- 6.70 399.60 +/- 40.00 518.00 +/- 51.80 414.40 +/- 41.40 836.20 +/- 83.62 604.00 +/- 60.40 357.05 +/- 35.70 117.66 +/- 11.78 37.00 +/- 3.70 38.85 + 3.90 699.30 +/- 69.90 46.88 - 87.06 279.72 - 519.48 362.60 - 673.40 290.08 - 538.72 585.34 - 1088.00 422.80 - 785.20 249.94 - 464.17 82.36 - 152.96 25.90 - 48.40 27.20 - 50.51 489.51 - 909.09 STAP-1 023 STAP-1 023 STAP-1 024 STAP-1 024 STAP-1 024 STAP-1024 e STAP-1 024 STAP-1 024 STAP-1 024 STAP-1024 STAP-1 024 STAP-1 024 STAP-1 024 STAP-1 024 Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 Gr. Alpha Gr. Beta Am-241 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 U-23314 U-238 Zn-65 0.06 +/- 0.02 1.37 +/- 0.08 0.08 +/- 0.03 2.07 +/- 0.06 2.11 +/- 0.08 1.78 +/- 0.08 1.76 +/- 0.08 2.84 +/- 0.11 0.12 +/- 0.01 0.08 +/- 0.01 0.66 +/- 0.19 0.23 +/- 0.03 0.23 +/- 0.03 3.90 +/- 0.22 0.40 +/- 0.04 1.20 +/- 0.12 0.10 +/- 0.01 2.40 +/- 0.24 2.30 +/- 0.23 2.90 +/- 0.29 2.00 +/- 0.20 3.00 +/- 0.30 0.13 +/- 0.01 0.09 +/- 0.01 0.80 +/- 0.08 0.21 +/- 0.02 0.22 +/- 0.02 4.00 +/- 0.40 0.00 - 0.80 0.60 - 1.80 0.07 - 0.13 1.68 - 3.12 1.61 - 2.99 2.03 - 3.77 1.40 - 2.60 2.10 - 3.90 0.09 - 0.17 0.06 - 0.12 0.56 - 1.04 0.15 - 0.27 0.15 - 0.29 2.80 - 5.20 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 water water water water water water water water water water water water water 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 Am-241 Co-57 Co-60 Cs-1 34 Cs-137 Fe-55 H-3 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 0.56 +/- 0.07 184.10 +/- 13.50 164.40 +/- 11.70 201.10 +/- 14.00 245.50 +/- 15.80 37.60 +/- 25.30 76.50 +/- 5.40 272.10 +/- 17.50 94.40 +/- 3.20 1.11 +/- 0.09 0.01 +/- 0.01 6.20 +/- 1.10 10.70 +/- 1.00 0.60 +/- 0.06 185.00 +/- 18.50 163.00 +/- 16.30 208.00 +/- 20.80 250.00 +/- 25.00 33.00 +/- 3.30 83.00 +/- 8.30 267.00 +/- 26.70 1 00.00 _ 1 0.00 1.20 +/- 0.12 0.00 +/- 0.00 7.00 +/- 0.70 10.00 +/- 1.00 0.42 - 0.78 129.50 - 240.50 114.10 - 211.90 145.60 - 270.40 175.00 - 325.00 23.10 - 42.90 58.10 - 107.90 186.90 - 347.10 70.00 - 130.00 0.84 - 1.56 0.00 - 0.10 4.90 - 9.10 7.00 - 13.00 A6-1

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity Limits' STW-1026 water 05/01/04 U-233/4 0.14 i 0.02 0.12 +/- 0.01 0.08 - 0.16 STW-1026 water 05/01/04 U-238 0.94 +/- 0.05 0.90 +/- 0.09 0.63 - 1.17 STW-1 026 water 05/01104 Zn-65 219.60 +/- 27.90 208.00 +/- 20.80 145.60 - 270.40 STW-1 027 water 05/01/04 Gr. Alpha 1.20 +/- 0.10 1.20 +/- 0.12 0.00 -2.40 STW-1027 water 05/01/04 Gr. Beta 4.30 i 0.10 4.10 +/- 0.41 2.05 - 6.15

' Results obtained by Environmental, Inc. Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho bAll results are in Bq/kg or BqIL as requested by the Department of Energy.

a MAPEP results are presented as the known values and expected laboratory precision (1 sigma,1 determination) and control limits as defined by the MAPEP.

d The cause of the deviation seems to be incomplete dissolution of the sample.

A spiked soil sample was prepared. Known activity; 32.98 pCig; laboratory result 33.47 pCilg.

The sample was reanalyzed with the same results. Investigation is in progress.

g Based on the results of gamma emitting isotopes (Cs-137 and Co-60), the filter geometry appears to be biased by -10%. Addition of the summation peak at 1400 KeV results in a recalculation of 2.12 +/- 0.15 Bq/sample.

A6-2

TABLE A-7. Environmental Measurehnents Laboratory Quality Assessment Piogram (EML)

Concentrationa EML Control Lab Code Type Date Analysis Laboratory results Resulte Limits' STW-1 009 STW-1 009 STW-1009 STW-1 009 STW-1009 STW-1009 STW-1 009 STW-1009 water water water water water water water water 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 Am-241 Co-60 Cs-I 37 H-3 Pu-238 Pu-239/40 Sr-90 Uranium 1.21 +/- 0.02 152.30 +/- 0.30 50.40 +/- 0.90 263.50 +/- 10.00 1.03 +/- 0.04 2.90 +/- 0.10 5.20 +/- 0.30 4.35 +/- 0.21 208.00 +/- 20.70 1063.00 +/- 27.00 1.31 163.20 51.95 186.60 1.10 3.08 4.76 4.62 326.00 1170.00 0.66 - 1.56 0.87 - 1.17 0.90 - 1.25 0.69 - 1.91 0.68 - 1.33 0.62 - 1.38 0.73 - 1.65 0.40 - 1.45 0.55 - 1.31 0.75 - 1.65 STW-1010 water STW-1010 water 03/01/04 Gr. Alpha 03/01/04 Gr. Beta STSO-1011 STSO-1011 STSO-1011 STSO-1011 STSO-1 011 STSO-1011 STVE-1012 STVE-1012 STVE-1012 STVE-1012 STVE-1012 STVE-1012 STAP-1013 STAP-1013 STAP-1013 STAP-1013 STAP-1013 STAP-1 013 STAP-1013 STAP-1013 Soil Soil Soil Soil Soil Soil Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 03/01/04 Am-241 Cs-I 37 K-40 Pu-239/40 Sr-90 Uranium Am-241 Co-60 Cs-137 K-40 Pu-239/40 Sr-90 Am-241 Co-60 Cs-1 34 Cs-1 37 Pu-238 Pu-239/40 Sr-90 Uranium 14.10 + 4.30 1292.00 + 13.00 563.00 +/- 83.00 20.70 +/- 1.10 72.10 +/- 5.80 139.10 +/- 10.20 4.50 +/- 0.20 14.10 +/- 0.40 573.90 +/- 6.00 709.00 +/- 19.30 6.60 +/- 0.50 766.50 +/- 51.30 0.11 +/- 0.01 30.90 +/- 1.08 12.30 +/- 1.30 24.90 +/- 0.60 0.04 +/- 0.01 0.17 +/- 0.02 1.80 +/- 0.20 0.17 +/- 0.01 1.09 +/- 0.06 2.68 +/- 0.05 13.00 1323.00 539.00 22.82 51.00 180.22 4.93 14.47 584.67 720.00 6.81 734.00 0.10 35.40 18.20 26.40 0.04 0.16 1.76 0.17 1.20 2.85 0.52 - 2.41 0.74 - 1.40 0.70 - 1.59 0.62 - 1.99 0.58 - 2.96 0.27 - 1.48 0.58 - 2.86 0.64 - 1.49 0.75 - 1.48 0.45 - 1.51 0.60 - 1.98 0.50 - 1.37 0.62 - 1.93 0.74 - 1.25 0.70 - 1.21 0.72 - 1.32 0.61 - 1.55 0.67 - 1.58 0.62 - 2.26 0.79 - 2.88 0.82 - 1.58 0.75 - 1.94 STAP-1014 Air Filter 03/01/04 Gr. Alpha STAP-1014 Air Filter 03/01/04 Gr. Beta

' Results are reported in Bq/L with the following exceptions: Air Filters (Bq/Filter), Soil and Vegetation (Bqlkg).

b The EML result listed is the mean of replicate determinations for each nuclide +/- the standard error of the mean.

c Control limits are reported by EML as the ratio of Reported Value / EML value.

c Probable effect of summation peaks and slight difference in filter geometry.

A7-1

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

2.0. Single Measurements Each single measurement is reported as follows:

x +/- s where:

x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: <L, where L = the lower limit of detection based on 4.66s uncertainty for a background sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; x1 i si and x2 + S2 Reported result:

x +/- s; where x = (1/2) (xI + x2) and s = (1/2) 3.2.

Individual results:

<LI, <L2 Reported result: <L, where L = lower of Li and L2 3.3.

Individual results:

x i s, <L Reported result:

x i s If x ŽL; 4L otherwise.

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed In the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers xj, x2... xn are defined as follows:

X=n Ex S=

n-i 4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.

4.5 In rounding off, the following rules are followed:

4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained number s are kept unchanged. As an example, 11.443 is rounded off to 11.44.

4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11 A45 is rounded off to 11.45.

B-2

POINT BEACH NUCLEAR PLANT APPENDIX C Sampling Program and Locations C-1

POINT BEACH NUCLEAR PLANT Locations Collection Type Analysis Sample Type No.

Codes (and Type)'

(and Frequency)b (and Frequency)b Airborne Filters Airbome Iodine Ambient Radiation (TLD's)

Lake Water Well Water Vegetation Shoreline Silt Soil Milk Algae Fish 6

E-1 -4,8,20 6

E-1-4, 8, 20 22 E-1-9,12,14-18,20, 22-32, 34-36,38,39 5

E-1,5,6,33 1

E-10 8

E-1-4, 6.9,20 5

E-1,5,6,8,9,12 8

E-1-4,6,8,9,20 3

E-11,40,21 2

E-5,12 1

E-13 Weekly Weekly Quarterly Monthly Quarterly 3x / year as available 2xlyear 2x I year Monthly 3x / year as available 3x I year as available GB, GS, on QC for each location 1-131 Ambient Gamma GB, BS, 1-131 on MC H-3, Sr-89-90 on QC GB, GS, H-3, Sr-89-90,1-131 GB, GS GB, GS GB, GS GS, 1-131, Sr-89-90 GB, GS GB, GS (in edible portions)

SPECIAL COLLECTIONS AND ANALYSES Airborne Filters Liquid Subsoil Water Miscellaneous Water Samples 4 per month I perquarter 1 per month 4 per quarter 4-5 per year Sr-89, Sr-90 Sr-89, Sr-90 (comp.)

GA, Sr-89, Sr-90 GA, GB, H-3, GS Sr-89, Sr-90

Locations codes are defined in Table 2. Control Stations are Indicated by (C). All other stations are indicators.

° Analysis type is coded as follows: GB = gross beta, GA = gross alpha, GS = gamma spectroscopy, H-3 = tritium, Sr-89 = strontium-89, Sr-90 = strontium-90,1-131 = iodine-131. Analysis frequency Is coded as follows:

MC = monthly composite, QC = quarterly composite.

C-2

ML051580480

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